ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller I MJW Technical Services

Page 1 of 95

DOE Review Release 04/07/2010

Document Title:

Los Alamos National Laboratory –

Occupational Environmental Dose

Document Number: ORAUT-TKBS-0010-4

Revision: 01

Effective Date: 03/26/2010

Type of Document: TBD

Supersedes: Revision 00

Subject Expert(s): Joel I. Cehn and Laura McDowell-Boyer 

Site Expert(s): N/A

Approval: Signature on File Approval Date: 03/22/2010

Donald N. Stewart, Document Owner

Concurrence: Signature on File Concurrence Date: 03/22/2010

John M. Byrne, Objective 1 Manager

Concurrence: Signature on File Concurrence Date: 03/22/2010

Edward F. Maher, Objective 3 Manager

Concurrence: Signature on File Concurrence Date: 03/23/2010

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 03/26/2010

James W. Neton, Associate Director for Science

New Total Rewrite Revision Page Change

FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR 

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 2 of 96

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION

NUMBER DESCRIPTION

10/08/2004 00 First approved new technical basis document for the Los Alamos 

National Laboratory – Occupational Environmental Dose. 

Incorporates formal internal and NIOSH review comments. Initiated 

by Jack E. Buddenbaum.

03/26/2010 01 Revision adds new environmental external and uptake data prior to 

1971. Added Attributions and Annotations section. Incorporated 

SEC-00061 and SEC-00051. Intakes to assign maximum doses for 

four primary radionuclides during the specified employment period for 

the class of Los Alamos National Laboratory employees added to the 

Special Exposure Cohort (1943–1975) are included. Section 4.1.3.3 

clarified ‘partial’ dose reconstruction with respect to ambient external 

dose; additional instructions to dose reconstructors were added to 

section 4.3.1, ‘Ambient Radiation.’ These state that on-site ambient 

dose is to be based on the environmental film badge and TLD results 

available from 1965 onward. In support of this, rows with years prior 

to 1965 were deleted from Table 4-26. Single correction to a 

preposition in Section 4.2.1. Incorporates review comments from 

formal internal and NIOSH review. Incorporates changes required by 

the adoption of an 83.14 SEC determination. This alters the 

definition of the class of Los Alamos National Laboratory employees 

added to the SEC (1943-1975), and removes the area-specific and 

monitoring restrictions from the class definition making the SEC class 

now include all employees in all areas of the LANL during the period 

1943-1975. Constitutes a total rewrite of the document. Training 

required: As determined by Objective Manager. Initiated by Donald 

N. Stewart.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 3 of 96

TABLE OF CONTENTS

SECTION TITLE

Acronyms and Abbreviations ...............................................................................................................

PAGE

7

4.1 Introduction ..............................................................................................................................9

4.1.1 Purpose......................................................................................................................10

4.1.2 Scope.........................................................................................................................10

4.1.3 Special Exposure Cohort............................................................................................10

4.1.3.1 September 1, 1944 through July 18, 1963.................................................... 10

4.1.3.2 March 15, 1943 through December 31, 1975 ............................................... 11

4.1.3.3 Partial Dose Reconstructions ....................................................................... 11

4.2 Internal Exposure from Onsite Atmospheric Radionuclide Concentrations ............................. 12

4.2.1 Onsite Releases to Air................................................................................................12

4.2.1.1 Emissions Data ............................................................................................ 12

4.2.1.1.1 Episodic Releases ...................................................................... 12

4.2.1.1.2 Bayo Canyon Releases .............................................................. 13

4.2.1.2 Radionuclides of Significance ...................................................................... 13

4.2.1.3 Estimation of Air Concentrations .................................................................. 16

4.2.1.4 Estimation of Occupational Intakes .............................................................. 17

4.2.1.4.1 Intakes, 1945 to 1970 ................................................................. 18

4.2.1.4.2 Intakes, 1971 to present ............................................................. 18

4.2.2 Resuspension.............................................................................................................18

4.3 External Exposure..................................................................................................................19

4.3.1 Ambient Radiation ......................................................................................................19

4.3.2 Release of Noble Gases.............................................................................................22

4.3.2.1 Omega Reactors TA-2 ................................................................................. 22

4.3.2.2 Los Alamos Neutron Science Center (TA-53)............................................... 23

4.4 Uncertainty.............................................................................................................................24

4.5 Attributions and Annotations .................................................................................................. 50

References ........................................................................................................................................52

ATTACHMENT A, SOURCE EMISSIONS......................................................................................... 55

ATTACHMENT B, SCREENING ESTIMATES................................................................................... 71

ATTACHMENT C, AIR CONCENTRATIONS .................................................................................... 73
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 4 of 96

ST OF TABLES

TABLE TITLE PAGE

4-1 Estimated annual average intakes of 241Am, 3

H, 239Pu, and 234U for TA-2............................... 26

4-2 Estimated annual average intakes of 241Am, 3

H, 239Pu, 232Th, 234U, MFP, and 

P/VAP for TA-3 ......................................................................................................................27

4-3 Estimated annual average intakes of 241Am, 3

H, 239Pu, and 234U for TA-5............................... 28

4-4 Estimated annual average intakes of 241Am, 3

H, 239Pu, and 234U for TA-6............................... 29

4-5 Estimated annual average intakes of 3

H for TA-9................................................................... 29

4-6 Estimated annual average intakes of 241Am, 3

H, 239Pu, and 234U for TA-11............................. 30

4-7 Estimated annual average intakes of 241Am, 3

H, 239Pu, and 234U for TA-15............................. 30

4-8 Estimated annual average intakes of 241Am, 3

H, 239Pu, and 234U for TA-16 ............................ 31

4-9 Estimated annual average intakes of 234U for TA-18............................................................... 31

4-10 Estimated annual average intakes of 241Am, 3

H, 239Pu, 234U, and MFP for 

TA-21.....................................................................................................................................32

4-11 Estimated annual average intakes of 241Am, 3

H, 239Pu, and 234U for TA-33............................. 33

4-12 Estimated annual average intakes of 241Am, 3

H, 239Pu, 234U, MFP, and 

P/VAP for TA-35 ....................................................................................................................34

4-13 Estimated annual average intakes of 241Am, 3

H, 239Pu, and 234U for TA-36............................. 35

4-14 Estimated annual average intakes of 3

H, 239Pu, and 234U for TA-39........................................ 35

4-15 Estimated annual average intakes of 3

H, 239Pu, and 234U for TA-41........................................ 36

4-16 Estimated annual average intakes of 241Am, 3

H, 239Pu, and 234U for TA-43............................. 37

4-17 Estimated annual average intakes of 234U for TA-46............................................................... 37

4-18 Estimated annual average intakes of 241Am, 239Pu, 234U, MFP, and P/VAP 

for TA-48................................................................................................................................38

4-19 Estimated annual average intakes of 241Am, 3

H, 239Pu, and 234U for TA-49............................. 39

4-20 Estimated annual average intakes of 241Am, 3

H, 239Pu, 232Th, 234U, and MFP 

for TA-50................................................................................................................................40

4-21 Estimated annual average intakes of 241Am, 3

H, 239Pu, 234U, and P/VAP for 

TA-53.....................................................................................................................................41

4-22 Estimated annual average intakes of 241Am, 3

H, 239Pu, and 234U for TA-54............................. 42

4-23 Estimated annual average and maximum intakes of 241Am, 3

H, 239Pu, 232Th, 

and 234U for TA-55..................................................................................................................43

4-24 Estimated annual average intakes of 239 Pu and MFPs from the general Los 

Alamos area...........................................................................................................................43

4-25 Estimated air concentrations from resuspension .................................................................... 44

4-26 Area badge data, annual TLD or film results .......................................................................... 44

4-27 Estimated annual deposition of 140La and doses from radioactive lanthanum 

experiments ...........................................................................................................................45

4-28 Estimated average external doses from 41Ar released from TA-2........................................... 46

4-29 Estimated average external doses from G/MAPs released from TA-53.................................. 47

4-30 Estimated average external doses at TA-21 and TA-72 from G/MAPs 

released from TA-53 .............................................................................................................. 48

4-31 Estimated annual site-wide maximum intakes and ambient dose rates for all 

radionuclides..........................................................................................................................49

A-1 Estimated source emissions from TA-1.................................................................................. 55

A-2 Estimated source emissions from TA-2.................................................................................. 55

A-3 Estimated source emissions from TA-3.................................................................................. 56

A-4 Estimated source emissions from TA-9.................................................................................. 57

A-5 Estimated source emissions from TA-10................................................................................ 57

A-6 Estimated source emissions from TA-15................................................................................ 58

A-7 Estimated source emissions from TA-16................................................................................ 59
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 5 of 96

A-8 Estimated source emissions from TA-18................................................................................ 59

A-9 Estimated source emissions from TA-21................................................................................ 60

A-10 Estimated source emissions from TA-33................................................................................ 61

A-11 Estimated source emissions from TA-35................................................................................ 62

A-12 Estimated source emissions from TA-36................................................................................ 63

A-13 Estimated source emissions from TA-39................................................................................ 63

A-14 Estimated source emissions from TA-41................................................................................ 64

A-15 Estimated source emissions from TA-42................................................................................ 64

A-16 Estimated source emissions from TA-43................................................................................ 65

A-17 Estimated source emissions from TA-46................................................................................ 65

A-18 Estimated source emissions from TA-48................................................................................ 66

A-19 Estimated source emissions from TA-50................................................................................ 67

A-20 Estimated source emissions from TA-53................................................................................ 68

A-21 Estimated source emissions from TA-54................................................................................ 69

A-22 Estimated source emissions from TA-55................................................................................ 70

B-1 Results of screening analysis to identify potentially significant contributors 

to inhalation dose...................................................................................................................71

C-1 Estimated average air concentrations for 239Pu for TA-1 ........................................................ 73

C-2 Estimated average air concentrations for 241Am, 3

H, 239Pu, and 234U for TA-2......................... 73

C-3 Estimated average air concentrations for 241Am, 3

H, 131I, 239Pu, 232Th, 234U, 

MFP, and P/VAP for TA-3 ...................................................................................................... 74

C-4 Estimated average air concentrations for 241Am, 3

H, 239Pu, and 234U for TA-5......................... 75

C-5 Estimated average air concentrations for 241Am, 3

H, 239Pu, and 234U for TA-6......................... 76

C-6 Estimated average air concentrations for 3

H for TA-9............................................................. 77

C-7 Estimated average air concentrations for 234U for TA-10 ........................................................ 77

C-8 Estimated average air concentrations for 241Am, 3

H, 239Pu, and 234U for 

TA-11.....................................................................................................................................78

C-9 Estimated average air concentrations for 241Am, 3

H, 239Pu, 232Th, and 234U 

for TA-15................................................................................................................................78

C-10 Estimated average air concentrations for 241Am, 3

H, 131I, 239Pu, and 234U for 

TA-16.....................................................................................................................................79

C-11 Estimated average air concentrations for 234U for TA-18 ........................................................ 80

C-12 Estimated average air concentrations for 241Am, 3

H, 131I, 239Pu, 234U, and 

MFP for TA-21 .......................................................................................................................80

C-13 Estimated average air concentrations for 241Am, 3

H, 131I, 239Pu, and 234U for 

TA-33.....................................................................................................................................82

C-14 Estimated average air concentrations for 241Am, 3

H, 239Pu, 234U, MFP, and 

P/VAP for TA-35 ....................................................................................................................83

C-15 Estimated average air concentrations for 241Am, 3

H, 239Pu, and 234U for 

TA-36.....................................................................................................................................84

C-16 Estimated average air concentrations for 3

H, 239Pu, and 234U for TA-39.................................. 85

C-17 Estimated average air concentrations for 3

H, 239Pu, and 234U for TA-41.................................. 86

C-18 Estimated average air concentrations for 239Pu for TA-42....................................................... 86

C-19 Estimated average air concentrations for 241Am , 3

H, 239Pu, and 234U for 

TA-43.....................................................................................................................................87

C-20 Estimated average air concentrations for 234U for TA-46 ........................................................ 88

C-21 Estimated average air concentrations for 241Am, 239Pu, 234U, MFP, and 

P/VAP for TA-48 ....................................................................................................................89

C-22 Estimated average air concentrations for 241Am, 3

H, 131I, 239Pu, and 234U for 

TA-49.....................................................................................................................................90

C-23 Estimated average air concentrations for 241Am, 3

H, 131I, 239Pu, 232Th, 234U, 

and MFP for TA-50.................................................................................................................91
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 6 of 96

C-24 Estimated average air concentrations for 241Am, 3H, 131I, 239Pu, 234U, and 

P/VAP for TA-53 ....................................................................................................................92

C-25 Estimated average air concentrations for 241Am, 3

H, 239Pu, and 234U for 

TA-54.....................................................................................................................................93

C-26 Estimated average air concentrations for Los Alamos general area, 1958 to 

1970.......................................................................................................................................94

C-27 Estimated average air concentrations for 241Am, 3

H, 239Pu, 232Th, and 234U 

for TA-55................................................................................................................................94

C-28 Estimated average annual air concentrations of 41Ar for TA-2 ................................................ 95

C-29 Estimated average annual air concentrations of G/MAPs for TA-53, TA-21, 

and TA-72 ..............................................................................................................................96

LIST OF FIGURES

FIGURE TITLE

4-1 Offsite, perimeter, and onsite AIRNET locations ....................................................................

PAGE

14

4-2 Offsite, perimeter, and onsite TLD locations........................................................................... 21

4-3 Average wind rose for five meteorological stations................................................................. 25
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 7 of 96

ACRONYMS AND ABBREVIATIONS

AMAD activity median aerodynamic diameter 

Bq becquerel

Ci curie

DOE U.S. Department of Energy

EEOICPA Energy Employees Occupational Illness Compensation Program Act of 2000

g gram

G/MAP gaseous/mixed activation product

hr hour

HYPO Water Boiler Reactor in high-power configuration

ICRP International Commission on Radiological Protection

km kilometer

LAHDRA Los Alamos Historical Document Retrieval and Assessment

LANL Los Alamos National Laboratory

LANSCE Los Alamos Neutron Science Center

LOPO Water Boiler Reactor in low-power configuration

m meter

MDA minimum detectable activity

MFP mixed fission product

mrem millirem

NCRP National Council on Radiation Protection and Measurements

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities

P/VAP particulate and vapor activation products

pCi picocurie

POC probability of causation

s second

SRDB Ref ID Site Research Database Reference Identification (number)

Sv sievert

TA technical area

TBD technical basis document

TLD thermoluminescent dosimeter

U.S.C. United States Code

yr year

μCi microcurie
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 8 of 96

μm micrometer

μrem microrem

§ section or sections
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 9 of 96

4.1 INTRODUCTION

Technical basis documents and site profile documents are not official determinations made by the 

National Institute for Occupational Safety and Health (NIOSH) but are rather general working 

documents that provide historic background information and guidance to assist in the preparation of 

dose reconstructions at particular sites or categories of sites. They will be revised in the event 

additional relevant information is obtained about the affected site(s). These documents may be used 

to assist NIOSH staff in the completion of the individual work required for each dose reconstruction.

In this document the word “facility” is used as a general term for an area, building, or group of 

buildings that served a specific purpose at a site. It does not necessarily connote an “atomic weapons 

employer facility” or a “Department of Energy [DOE] facility” as defined in the Energy Employees 

Occupational Illness Compensation Program Act [EEOICPA; 42 U.S.C. § 7384l(5) and (12)]. 

EEOICPA defines a DOE facility as “any building, structure, or premise, including the grounds upon 

which such building, structure, or premise is located ... in which operations are, or have been, 

conducted by, or on behalf of, the Department of Energy (except for buildings, structures, premises, 

grounds, or operations ... pertaining to the Naval Nuclear Propulsion Program)” [42 U.S.C. § 

7384l(12)]. Accordingly, except for the exclusion for the Naval Nuclear Propulsion Program noted 

above, any facility that performs or performed DOE operations of any nature whatsoever is a DOE 

facility encompassed by EEOICPA.

For employees of DOE or its contractors with cancer, the DOE facility definition only determines 

eligibility for a dose reconstruction, which is a prerequisite to a compensation decision (except for 

members of the Special Exposure Cohort). The compensation decision for cancer claimants is based 

on a section of the statute entitled “Exposure in the Performance of Duty.” That provision [42 U.S.C. § 

7384n(b)] says that an individual with cancer “shall be determined to have sustained that cancer in the 

performance of duty for purposes of the compensation program if, and only if, the cancer ... was at 

least as likely as not related to employment at the facility [where the employee worked], as 

determined in accordance with the POC [probability of causation1

The statute also includes a definition of a DOE facility that excludes “buildings, structures, premises, 

grounds, or operations covered by Executive Order No. 12344, dated February 1, 1982 (42 U.S.C. 

7158 note), pertaining to the Naval Nuclear Propulsion Program” [42 U.S.C. § 7384l(12)]. While this 

definition excludes Naval Nuclear Propulsion Facilities from being covered under the Act, the section 

of EEOICPA that deals with the compensation decision for covered employees with cancer [i.e., 42 

U.S.C. § 7384n(b), entitled “Exposure in the Performance of Duty”] does not contain such an 

exclusion. Therefore, the statute requires NIOSH to include all occupationally-derived radiation 

exposures at covered facilities in its dose reconstructions for employees at DOE facilities, including 

radiation exposures related to the Naval Nuclear Propulsion Program. As a result, all internal and 

external occupational radiation exposures are considered valid for inclusion in a dose reconstruction. 

No efforts are made to determine the eligibility of any fraction of total measured exposure for inclusion 

in dose reconstruction. NIOSH, however, does not consider the following exposures to be 

occupationally derived (NIOSH 2007a):

] guidelines established under 

subsection (c) ...” [42 U.S.C. § 7384n(b)]. Neither the statute nor the probability of causation 

guidelines (nor the dose reconstruction regulation, 42 C.F.R. Pt. 82) define “performance of duty” for 

DOE employees with a covered cancer or restrict the “duty” to nuclear weapons work (NIOSH 2007a).

• Background radiation, including radiation from naturally occurring radon present in 

conventional structures

 1 The U.S. Department of Labor (DOL) is ultimately responsible under the EEOICPA for determining the POC.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 10 of 96

• Radiation from X-rays received in the diagnosis of injuries or illnesses or for therapeutic 

reasons

4.1.1

The purpose of this TBD is to describe potential occupational environmental dose to Los Alamos 

National Laboratory (LANL) workers. Occupational environmental exposure refers to exposures 

workers received while on the site but outside facilities from elevated ambient radiation, from facility 

effluent releases to the environment, and from resuspension of radionuclides in soils. Effluent 

releases can result in internal and external exposures by inhalation of airborne radionuclides and by 

submersion in an effluent. This TBD provides estimated annual intakes for inhalation exposure and 

estimated doses as a result of submersion and ambient exposure at LANL.

Purpose

4.1.2

As discussed in Part 2 of the LANL Site Profile (ORAUT 2004), operations at Los Alamos have 

occurred in land divisions called technical areas (TAs). Table 2-1 of Part 2 lists each TA with 

information on the types of radionuclides that were present at some time during operations there. 

Activities that have occurred at LANL since operations began in 1943 have been highly variable on 

the site and over time. This TBD addresses occupational environmental exposure by considering 

available source term information that has been compiled for some of the TAs, as well as results of 

published environmental measurements for a larger number of TAs.

Scope

This analysis recognized that effluents from a particular LANL TA would have the greatest impact on 

workers in that TA, but that such effluents could affect workers in nearby TAs. A comprehensive sitewide atmospheric model for predicting onsite worker exposures from the highly variable releases of 

radionuclides to the air would be useful for evaluating these impacts, but LANL has not developed 

such a model. This TBD relies to a great extent on environmental measurements (i.e., air-monitoring 

data), and to a lesser extent on source term emission estimates, to estimate worker exposures. 

Environmental measurements do not distinguish the source of emissions and, therefore, reflect air 

concentrations from nearby as well as more distant sources. The emissions estimates are useful in 

filling in some gaps in measurement data, and they are critical to estimating exposures that occurred 

before the start of comprehensive and routine measurement data reports.

4.1.3

Based on the findings and recommendations of NIOSH and the Advisory Board on Radiation and 

Worker Health, the Secretary of the U.S. Department of Health and Human Services (HHS) has 

determined that, for the period of March 15, 1943, through December 31, 1975, internal doses for 

certain employees may not be feasibly reconstructed. For this reason, two classes of employees of 

the LANL have been added to the Special Exposure Cohort. NIOSH has subsequently proposed a 

revision to the class for the period March 15, 1943, through December 31, 1975 which removes the 

area-specific and monitoring requirements from the class definition. 

Special Exposure Cohort

4.1.3.1 September 1, 1944 through July 18, 1963

NIOSH and the Advisory Board on Radiation and Worker Health have determined that it is not 

feasible to reconstruct internal doses for workers involved in the radioactive lanthanum (RaLa) 

program, due to a lack of bioassay monitoring or other workplace measurements that would allow the 

reconstruction of individual doses or some maximum dose. For this reason, the Secretary of HHS has 

added the following class of employees to the Special Exposure Cohort (NIOSH 2006).
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 11 of 96

Employees of the Department of Energy, predecessor agencies, and their 

contractors or subcontractors who were monitored or should have been monitored 

for exposure to ionizing radiation associated with radioactive lanthanum (RaLa) 

operations at Technical Area 10 (Bayo Canyon Site), Technical Area 35 (Ten Site) 

and Buildings H, Sigma, and U (located within Technical Area 1) at the Los Alamos 

National Laboratory (LANL) for a number of work days aggregating at least 250 

work days during the period from September 1, 1944, through July 18, 1963, or in 

combination with work days within the parameters established for one or more 

other classes of employees in the SEC.

4.1.3.2 March 15, 1943 through December 31, 1975

Internal dose reconstruction was found not to be feasible for an additional class of employees of LANL 

due to the absence of bioassay monitoring or other workplace measurements for the potential intake 

of certain radionuclides associated with radioactive material use in a number of Technical Areas. For 

this reason, the Secretary of HHS added a class of employees to the Special Exposure Cohort

(NIOSH 2007b).

Employees of the Department of Energy predecessor agencies and their contractors or 

subcontractors who were monitored or should have been monitored for radiological 

exposures while working in operational Technical Areas with a history of radioactive 

material use at the Los Alamos National Laboratory (LANL) for a number of workdays 

aggregating at least 250 work days during the period from March 15, 1943, through 

December 31, 1975, or in combination with work days within the parameters established 

for one or more other classes of employees in the SEC.

Subsequently, NIOSH has proposed a modified class to remove the area-specific and monitoring 

requirements from the class definition (ref the new 83.14 ER when approved by OCAS).

All employees of the Department of Energy, its predecessor agencies, and their 

contractors and subcontractors who worked at the Los Alamos National Laboratory in Los 

Alamos, New Mexico, from March 15, 1943 through December 31, 1975, for a number of 

work days aggregating at least 250 work days, occurring either solely under this 

employment or in combination with work days within the parameters established for one or 

more other classes of employees included in the Special Exposure Cohort.

4.1.3.3 Partial Dose Reconstructions

NIOSH has determined that it is possible to reconstruct or bound external doses and occupational 

medical X-ray dose and therefore individuals with non-presumptive cancers, or who do not meet the 

definitions of the classes of employees added to the SEC, can be considered for partial dose 

reconstructions, including doses from environmental radioactive material on-site ambient dose-rate 

fields in years for which data are available. 

As documented by NIOSH (2007b), partial dose reconstructions can include internal dose from tritium 

(from 1950 onward), polonium (from 1944 to 1956), plutonium (from 1944 onward), and uranium (from 

1943 onward) when based on records of bioassay monitoring. These radionuclides were likely to 

compose a part of the internal dose received by LANL employees from intake of radionuclides from 

the general environment. Although for later years data are available to characterize environmental 

internal doses in great detail, such data are not available, typically, for years before 1971. On-site 

ambient doses may be included in partial dose estimates for years in which they may be based on a 

consistent environmental dose measurement program, specifically, 1965 and later. 
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 12 of 96

4.2 INTERNAL EXPOSURE FROM ONSITE ATMOSPHERIC RADIONUCLIDE 

CONCENTRATIONS

4.2.1

In Part 2 of the LANL Site Profile (ORAUT 2004), Table 2-1 lists LANL TAs and potential sources of 

radioactive materials that are or were present at some time at each TA. Enriched and depleted 

uranium, as well as plutonium isotopes, are commonly listed sources. Due to the many different types 

of applied research that have been conducted at LANL, Table 2-1 also lists tritium, noble gases, and 

fission and activation products. 

Onsite Releases to Air

LANL has reported effluents for many of the TAs from 1971 to 1995 [1]. In recent years, the reporting 

of air emissions has been by stack or vent. It is not possible to ascertain at this point how 

comprehensive the current reporting of effluents is. Estimates of emissions from the Omega Reactors 

(TA-2), for example, have not been obtained. Furthermore, LANL has not assessed the exact 

locations of releases in relation to potential receptors in a TA. 

An ambient air-monitoring program at LANL began as early as 1954 with a single station on the roof

of the Administration Building in TA-3 (Johnson 1954). In 1959, a network of about 15 stations was 

put into operation. At present, about 60 stations conduct continuous air sampling. About 20 of the 

presently operational stations are on the site, with the remainder being offsite or perimeter stations. 

Figure 4-1 shows the location of active onsite and offsite monitoring stations. Historical results of the 

AIRNET monitoring network through 2000 are available on the LANL Web site (LANL 2003), and 

annual environmental surveillance reports summarize yearly results. However, results are not 

reported for many TAs, and data are missing for some radionuclides and some years. Locations of 

the air-monitoring stations in relation to a specific worker location in a TA are not well known.

Due to the lack of comprehensiveness of both effluent and air-monitoring data, the approach to 

estimation of worker intakes of radionuclides from air due to emissions from the TAs relied on a 

combination of the effluent and air-monitoring data in this TBD. Because air-monitoring data from a 

TA include concentrations from effluents from that TA as well as resuspension of previously deposited 

radionuclides and effluents from nearby TAs, this analysis preferred these data for estimation of air 

concentrations and ultimately worker intakes. The analysis used emissions data to fill some of the 

known gaps in monitoring data (see Section 4.2.1.3).

4.2.1.1 Emissions Data

Tables A-1 through A-22 in Attachment A list emissions data. The tables list source emissions data 

by year and TA. If effluents were reported by stack or building vent (1971 to present), the tables sum 

effluents from the stacks and vents in each TA. For earlier years (1943 to 1970), the effluent releases 

in this document rely on data from the Centers for Disease Control and Prevention Los Alamos 

Historical Document Retrieval and Assessment (LAHDRA) project (ENSR 2002), including 

unpublished data; however, these data were determined to be insufficient for reconstruction of 

environmental internal doses.

4.2.1.1.1 Episodic Releases

LANL reported accidental releases of tritium and plutonium in the 1970s. Before that time, LANL 

noted some accidental releases (for example, a fire at TA-21 in July 1957), but accurate release 

estimates were not available (ENSR 2002). There were two tritium releases from TA-3 and one from 

TA-33. There was a plutonium release from TA-21 in October 1970 (ENSR 2002). The emissions 

estimates (Tables A-1 through A-22 in Attachment A) include these and other episodic releases for 

which data were available along with routine stack releases for those years.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 13 of 96

4.2.1.1.2 Bayo Canyon Releases

Experiments in TA-10, Bayo Canyon, involved detonation of explosives around radioactive materials. 

These detonations dispersed materials, principally 140La, to the atmosphere and could have caused 

exposure to LANL employees. The dominant dose pathway would have been exposure to gamma 

radiation from 140La that was deposited on the ground (i.e., groundshine). An analysis by Kraig (1997) 

of offsite exposures to 140La as a result of these detonations indicated that the groundshine dose 

contribution was approximately 3 orders of magnitude higher than that from inhalation and immersion 

in the contaminated air.

4.2.1.2 Radionuclides of Significance

Before describing how air concentrations in the TAs from emissions and monitoring data were 

estimated in this analysis, it is important to focus the analysis on radionuclides that are potentially 
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 14 of 96

Figure 4-1. Offsite, perimeter, and onsite AIRNET locations (LANL 2002, p. 167).
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 15 of 96

significant to dose. The basis for selection of radionuclides for estimating air concentrations were 

screening calculations (see Table B-1 of Attachment B) to estimate which radionuclides that were 

listed as effluents were likely to contribute to at least 95% of the worker’s total effective 50-year 

committed dose during each year [2]. Because the assumptions in screening overestimate potential 

exposures, it is believed these criteria correctly eliminate insignificant radionuclides from further 

concern.

The screening analysis evaluated the potential inhalation dose from the maximum annual reported 

emission of each radionuclide for the entire site (listed by TA in Tables A-1 through A-22). In this 

analysis, inhalation dose was calculated for each radionuclide by estimating maximum air 

concentrations using a screening-level dispersion model (NCRP 1996). An annual inhalation rate of 

3,400 m3

/yr was assumed, which corresponds to continuous moderate activity (1.7 m3/hr) over a 

2,000-hour work year. The effective dose factors for each radionuclide are from the CD supplement 

to International Commission on Radiological Protection (ICRP) Publication 68 (ICRP 2001). An 

activity median aerodynamic diameter (AMAD) of 5 μm was assumed for all airborne particulates [3]. 

For elements, or groups of elements, for which isotopes were not specified [i.e., plutonium, uranium, 

mixed fission products (MFP), and particulate and vapor activation products (P/VAP)], a 

representative dose factor was selected that maximized the dose calculations for that group [4]. 

The National Council on Radiation Protection and Measurements (NCRP) screening model chosen for 

these calculations (NCRP 1996) is a simple dispersion model that accounts for potential increases in 

exposure due to building wake effects for close-in receptors (i.e., those less than 100 m from the 

source location). A calculated generic dispersion factor represents the ratio of air concentration (χ) to 

emission rate (Q) for any radionuclide:

χ/Q = f/(πuhk) s/m3 (4-1)

where:

χ = concentration at receptor (Ci/m3

)

Q = stack or building vent release rate (Ci/s)

f = wind frequency

u = wind speed (m/s)

h = height of effluent release (m)

k = constant (m)

The values that were used for the independent factors f and k correspond to defaults in NCRP (1996), 

such that f is assumed equal to 0.25 (the maximum frequency for any compass point), and k is 1 m. 

The calculation assumed an average wind speed u of 2.8 m/s and an average effluent release height 

h of 8 m. The average wind speed at Los Alamos has been reported to be about 2.8 to 3 m/s (LANL 

1994, 1999). The specification of an effluent release height of 8 m results in a dispersion factor that is 

more favorable to claimants because this assumes that releases are near ground level, rather than 

from elevated stacks, which increases estimated ground level concentrations. The calculated 

dispersion factor was 0.0036 s/m3

. 

The maximum dose calculations for each isotope (or representative isotope), were summed for each 

year (Table B-1). The yearly contributions of each isotope to the collective annual dose were 

evaluated to identify which radionuclides collectively contributed 95% or more of the yearly dose. The 

results of this comparison are given in Table B-1. The other radionuclides that collectively contributed

less than 5% of the yearly dose were considered relatively insignificant in relation to inhalation dose. 

The analysis indicated that the relatively significant radionuclides for which intakes should be 

evaluated were 3

H, 140La, 232Th, uranium, plutonium, and the groups of radionuclides specified as 
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 16 of 96

MFPs and P/VAPs. The uranium isotopes include 234U, 235U, and 238U, and the plutonium isotopes 

include 238Pu, 239Pu, 240Pu, 241Pu, and 241Am, according to the emissions estimates.

4.2.1.3 Estimation of Air Concentrations

Air-monitoring data, when available, formed the basis for estimates of air concentrations at each TA 

[5]. For some areas, especially TA-21 and TA-54, more than one monitoring station was active during 

many years (LANL 2003). In these cases, the analysis averaged concentrations over all stations in 

the TA. For years and locations when monitoring data were not available, the analysis based an 

estimate on the relationship between source emission rate and air concentration for years when data 

were available. 

Some concentration data for years before 1971 were available for this analysis. For some TAs, air 

concentration data were not available for any year or for many of the years after 1970. Therefore, a 

method had to be devised to provide reasonable estimates of air concentrations for those years at 

those TAs. For other instances, LANL reportedly discontinued analysis in some years for selected 

radionuclides they deemed insignificant.

For TA-3 and TA-21, both ambient air-monitoring data and release estimates for plutonium were 

available for several years of interest. Based on the relationship between plutonium air 

concentrations and releases for these TAs, a ratioing method was developed to estimate 

concentrations in other TAs where effluent estimates were available but ambient air-monitoring data 

were absent [6]. This method involved calculating the average ratio of plutonium air concentration to 

the estimated emission rate over all years for which both quantities were available. For TA-3, this 

average ratio (from 14 years of data) was 2.2 × 10-12 pCi/m3 per pCi/yr released. The maximum ratio 

for that period was 2.9 × 10-11 pCi/m3 per pCi/yr released. A regression analysis gave a correlation 

coefficient r of 0.93, which indicates a strong correlation between source emission rate and measured 

air concentrations for TA-3. For TA-21, this average ratio (from 25 years of data) was also 2.2 × 10-12

pCi/m3 per pCi/yr released. The maximum ratio for TA-21 was 1.4 × 10-11 pCi/m3 per pCi/yr released. 

A regression analysis of the TA-21 data gave a correlation coefficient r of 0.65 for the TA-21 ratios, 

which indicates a moderate correlation [7].

While this ratioing method requires the assumption that dispersion at all TAs is similar to that in TA-21 

and TA-3, that same assumption would be required of a simplistic model such as the one used for 

screening. Therefore, the ratioing method provides a reasonable estimate of average air 

concentrations at the LANL TAs for years in which monitoring results were not available [8]. Because 

the average ratio tends to reflect the strong influence of one or two high ratios during the represented 

periods, this method provides a reasonable estimation of concentrations that would result in a value 

more favorable to the claimant than a more in-depth modeling effort might produce. Furthermore, the 

use of maximum site-wide intakes for environmental dose lessens the likelihood of underprediction. 

This ratio of plutonium air concentration to plutonium source emission rate, with units of years per 

cubic meter, was used to estimate air concentrations of all radionuclides at TAs for years for which 

ambient monitoring data were not available. The reason for not developing separate ratios for other 

radionuclides is that monitoring data tended to be more limited for most other radionuclides (with the 

exception of 3

H). The justification for applying the plutonium ratios to other radionuclides showed in 

the calculated ratios for other radionuclides when monitoring data were available. For 3

H, the average 

of 88 ratios of measured air concentration to source emission rate was 1.7 × 10-12 yr/m3

, with a 

maximum ratio of 3.8 × 10-11 yr/m3

. For uranium, the average of 13 ratios of measured air 

concentration to source emission rate was 2.3 × 10-12 yr/m3

, with a maximum ratio of 1.9 × 10-11 yr/m3. 

The ratios for 3

H and uranium are very similar to those calculated for plutonium; therefore, the 

plutonium values can reasonably be applied for estimating air concentrations for all radionuclides of 

significance. 
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 17 of 96

Tables C-1 to C-26 in Attachment C list estimated average air concentrations for selected TAs. Table 

C-27 lists estimated average air concentration by year because TA data was not produced. The 

selected TAs correspond to those for which either monitoring data were available or source emissions 

were listed in Tables A-1 through A-22. To summarize, when monitoring data were available, average 

air concentrations represent annual measured results from AIRNET monitoring stations (LANL 2003). 

In the absence of monitoring data, the tables list estimated air concentrations that correspond to the 

ratioing method that is described above, using the ratios developed for plutonium. Footnotes to the 

tables indicate when the ratioing method was applied. 

In years before 1992, the monitoring data did not report concentrations of uranium in an isotopespecific manner. That is, the data reported concentrations as mass of uranium element per unit 

volume. In this case, the analysis made an assumption about the isotopic makeup of the uranium to 

convert to units of radioactivity. Assuming the mass concentration of uranium corresponds to the 

isotopic makeup of enriched uranium, which exhibits a higher specific activity than depleted or natural 

uranium due largely to the increase in the amount of 234U present (DOE 2001), the activity 

concentration of uranium was maximized [9]. Assuming an isotopic ratio, in atom percent, of 

0.02%:2.96%:97.02% for 234U:235U:238U, the specific activity of enriched uranium (activity of uranium 

per mass) is 1.55 × 10-6 Ci/g. This specific activity was used to convert uranium mass concentration 

to activity concentration, and once this conversion is made, the approach is to assume all uranium 

activity is 234U because the dose factor for 234U is slightly higher than those for 235U and 238U. Thus, 

Tables C2-C5, C7-C17, C19-C25, and C-27, report all uranium activity as 234U.

The air-monitoring data listed concentrations of plutonium isotopes separately for 238Pu and 239Pu. 

Rather than track the concentrations separately, there was a decision to add activities for both 

isotopes and report them as 239Pu, which has a slightly higher dose coefficient. Thus, Tables C-1 

through C-27 report all plutonium or alpha as 239Pu.

Tables C-1 through C-27 sometimes list the MFP and P/VAP categories. MFPs include 

predominantly 90Sr and 137Cs. The P/VAP group includes 73,74As, 76,77r,82Br, 68Ga, 68Ge, 193,195m,197Hg, 

and 75Se (LANL 2000). For simplicity, the entire intake from each category should be assumed to be 

composed solely of the radionuclide that results in the highest dose. Brackett (2010) ran comparisons 

for the radionuclides in the lists based on ICRP (1995) dose coefficients. For the MFP source term, 

the dose reconstructor should select 137Cs for most organs and 90Sr for the bone and red bone 

marrow. For the P/VAP category, either 68Ge, Type M, or 75Se, Type F, should be used based on 

which of the two results in the higher dose.

4.2.1.4 Estimation of Occupational Intakes 

The following discussion addresses estimation of two different sets of occupational intakes: intakes 

from 1945 to 1970, for which air-monitoring data were not available in a consistent format (i.e., before 

formal annual environmental reports), and intakes from 1971 to the present, for which monitoring data 

became more consistently available.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 18 of 96

4.2.1.4.1 Intakes, 1945 to 1970

As stated above, the period 1945 through 1970 is enveloped by the SEC period for the LANL, and it is 

not necessary to estimate environmental internal doses for the purpose of partial dose reconstruction 

during this period. Only partial dose reconstructions are possible in the pre-1976 time frame. Such 

partial dose reconstructions will include internal dose based only on internal dose monitoring data, in 

addition to external doses. 

4.2.1.4.2 Intakes, 1971 to present

Using the average air concentrations from Tables C-1 to C-27 of Attachment C, this analysis 

estimated annual inhalation intakes in becquerels per year for each radionuclide and TA for years 

after 1970 by assuming a breathing rate of 2,400 m3

/yr based on an occupancy of 2,000 hr/yr. Tables 

4-1 to 4-23 list the annual intakes for each TA by year, and Table 4-31 lists site-wide maximum

intakes, which represent the yearly maximums of all averages across the LANL for each radionuclide. 

Even from the post-1970 monitoring and emissions data, intake values for all radionuclides for every 

year were not available for many of the TAs. In cases where only a few years of data were missing 

for a given radionuclide, but the trend indicated that operations had probably not changed, this 

analysis made an estimate based on data in other years. The footnotes of Tables 4-1 through 4-23

indicate the basis for this type of estimate. If there was no clearly established trend, such estimates 

could not be made. Some of the gaps might exist because previous measurements indicated further 

yearly monitoring for a particular radionuclide was not warranted based on previous low-level 

measurements or estimates. Further, some TAs probably were not in operation at the time of the data 

gap. 

Section 4.2.1.3 describes specific representative isotopes for the MFP and P/VAP groupings, which 

are listed in the footnotes of tables that contain these designations. To calculate doses for these 

groupings, dose reconstructors should use the dose factor for the specified representative 

radionuclide. 

Information on solubility and particle sizes was not available for the radionuclides in Tables 4-1 to 

4-23. Therefore, dose reconstructors should assume that all activity intakes are respirable and should 

make selections of solubility designations to maximize the dose to the organ of interest in the absence 

of relevant solubility data. An AMAD of 5 μm, consistent with ICRP 68 (ICRP 1995) default 

recommendations, should be assumed for environmental particulates because no site-specific 

information to the contrary has been identified.

4.2.2

Resuspension of radionuclides from contaminated soil has been a potential source of internal dose to 

workers at LANL since the beginning of operations. A work area in which radionuclide emissions took 

place is a potential area of exposure to resuspended radionuclides that were deposited on the soil. 

The radionuclide emissions in Tables A-1 through A-22 do not include contributions from resuspended 

soil. Resuspension is generally more important for recently contaminated soil than for soil with older 

contamination because erosion and downward migration of radionuclides from the upper soil layers 

diminish the source term over time. In Section 4.2.1, measured concentrations of radionuclides are 

the basis for the estimates of intake in the listed TAs; these estimates include resuspended 

radionuclides at those TAs.

Resuspension

In its early years of operation, LANL discharged liquid effluents from TA-1, TA-21, and TA-50 

(formerly TA-35 and TA-45) to Acid, Pueblo, Los Alamos, and Mortandad Canyons. These canyon 

areas became contaminated with radionuclides. Due to the extent of soil contamination, these areas 
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 19 of 96

pose the greatest potential for significant historical intake from resuspension, particularly if recently 

contaminated soil was exposed to wind erosion or excavation activities. In addition, experiments with 

radioactive lanthanum in Bayo Canyon (TA-10) led to contamination of soil. The canyon areas are 

presently not part of work areas in any TA. LANL had decommissioned the TA-10 worksite by 1963, 

at which time it had cleaned up surface debris and excavated contaminated waste disposal facilities 

(LASL 1979). With the exception of TA-10, TA-21, and TA-50, TAs at LANL received minor 

contamination, if any (Kennedy and Purtymun 1971a). Nevertheless, if workers spent significant time 

in these canyons in areas where air-monitoring was not conducted, dose reconstructions should 

consider intakes and exposures from resuspension.

LANL has investigated resuspension in Acid, Pueblo, and Bayo Canyons (Ferenbaugh et al. 1982; 

LASL 1979). Table 4-25 lists estimated air concentrations of selected radionuclides in the canyons for 

conditions during the 1970s. For Mortandad and Los Alamos Canyons, information on soil 

contamination levels is available for estimation of resuspension (Purtymun, Stoker, and Peters 1980); 

this study indicated that plutonium isotopes, 137Cs, and 90Sr were found in soil during the 1970s at 

levels in excess of those that would be expected due to fallout. Estimates of air concentrations 

require the application of a resuspension factor to the measured levels. Assuming a resuspension 

factor of 1 × 10-9

/m (LASL 1979; Kennedy and Purtymun 1971b; Purtymun, Stoker, and Peters 1980), 

Table 4-25 lists estimated air concentrations for these areas. 

4.3 EXTERNAL EXPOSURE

4.3.1

More than 30 years of environmental monitoring reports (for example, LASL 1959, 1960) contain 

measured ambient gamma radiation levels. Figure 4-2 shows the network of thermoluminescent 

dosimeters (TLDs) currently in use at LANL for this purpose. Table 4-26 lists data for TA-3, TA-18, 

TA-53, and TA-54. TA-36 reported elevated exposures from experiments at TA-18 for several years. 

All of these areas recorded gamma doses above natural background (terrestrial and cosmic) 

radiation. Results are cumulative millirem per year based on 8,760 hours. A conversion factor is 

provided with Table 4-26 to convert these values to an annual dose based on 2,080 hours. The TLD 

results demonstrate the gamma-shine influence on other monitoring stations from the critical 

assembly experiments in TA-18. LANL environmental TLD data has a lognormal distribution. Sitewide maximum and geometric mean values are presented and are based on results from these four 

TAs. LANL annual reports present site background doses, and those are presented in Table 4-26. If 

no background is given, a 10-year average of reported site background is presented. 

Ambient Radiation

Individual TA data are available only for 1965 and after. However, periodic H-Division Progress 

Reports give sporadic monthly data from 1959. These reports indicate that initially 65 film badges 

were placed around the county and then, in September of 1959, approximately 25 stations were 

added. By 1965, 100 area badges were in use at LANL and in the Los Alamos area; attempts to 

locate these data have been unsuccessful. For partial dose reconstructions, data from 1965 and later 

have been determined to provide a sufficient basis for the estimation of on-site ambient doses. From 

1965 through 1970, only site-wide maximum doses are available. 

Eight H-Division Monthly Progress reports indicate an increase in environmental gamma dose at 

locations around the East Gate Laboratory in 1960 and 1961. This higher environmental dose was 

due to a 120-Ci 60Co source in the laboratory. The highest recorded value was 6.6 R during the first 

three quarters of 1961 – the source was then removed (Courtwright, Dummer, and Taschner 1996). 

Reports from those years state that 100 area (film) badges were used in 1959 and 1960 and gave 

1-year results of "less than 0.5 rem/yr" (LASL 1959, 1960). Reports indicate that elevated gamma 

levels occurred in the early years of TA-2 activities (ENSR 2002). No ‘typical’ external doses may be 
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 20 of 96

reliably inferred from these inconsistent reports, so on-site ambient doses are applied from the 

available data on the environmental dose measurements from 1965 onward. 
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 21 of 96

Figure 4-2. Offsite, perimeter, and onsite TLD locations (LANL 2002, p. 81).
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 22 of 96

A special survey found elevated ambient radiation in Acid Canyon, which LANL used from 1951 to 

1964 for liquid waste discharge from TA-45. LANL remediated the contaminated parts of Acid 

Canyon in 1967. Radiation data from before that time were not available. Data that are available 

indicate that in 1978 two areas of the canyon still exhibited elevated gamma dose rates. The areas 

are characterized by steep cliffs and were not routine work locations. Nevertheless, if workers spent 

significant time in these areas, exposures are possible. The above-background dose rates LANL 

reported for 1978 were 1.1 μrem/hr on average with a maximum of 50 μrem/hr (Ferenbaugh et al. 

1982). Before remediation in 1967, dose rates in the canyon could have been an order of magnitude 

higher.

The annual site-wide maximum ambient radiation dose rates are given in Table 4-31 along with the 

side-wide maximum intakes. These dose rates can be used if worker location during the period of 

employment is not accurately known.

Bayo Canyon Releases

Experiments from 1944 to 1962 in TA-10, Bayo Canyon, involved detonation of explosives around 

radioactive materials. These detonations dispersed materials, principally 140La, to the atmosphere 

and could have caused exposure to LANL workers. LANL has studied the impacts of these 

experiments extensively (Courtwright, Dummer, and Taschner 1996). Although the focus was on 

impacts off the LANL site, that analysis examined a receptor at the town site (TA-0). These results 

are applicable to LANL workers in TA-0, TA-2, TA-21, TA-35, TA-41, TA-43, TA-48, TA-53, TA-60, 

and TA-61 to the extent that these TAs were occupied during the years of the tests. 

Exposures are weighted by direction from TA-10. The prevailing wind direction is from Bayo Canyon 

to the west and north (that is, away from the Laboratory). On average, the wind carried 140La to the 

east (TA-0) and to the southeast (TA-2, etc.) about 3% of the time, so no adjustment for wind 

frequency is necessary. The distance to the receptor at TA-0 is 2.9 km, which is less than distances 

to the other TAs. An adjustment for distance is not possible from the available information. 

Therefore, the LANL-calculated impacts for TA-0 apply to nearby TAs. More distant TAs would have 

impacts at least 1 order of magnitude smaller.

Table 4-27 lists calculated doses to the receptor at TA-0, TA-2, and vicinity for 1945 to 1960 (Kraig 

1997). The dominant dose pathway would be exposure to gamma radiation from 140La deposited on 

the ground. Other pathways such as inhalation and other radionuclides are much less important 

(Kraig 1997). In addition to dose, Table 4-27 lists the annual average depositions that were 

calculated from the available information.

4.3.2

TA-2 (nuclear reactor area) and TA-53 [Los Alamos Neutron Science Center (LANSCE) accelerator] 

have a history of noble gas releases. The following sections describe the estimation of external dose 

from these releases.

Release of Noble Gases

4.3.2.1 Omega Reactors TA-2

The Omega reactors in TA-2 were in operation from 1944 to 1992, and during that time they emitted 

predominantly noble gases. LANL did not routinely measure effluents from the Omega reactors [the 

Water Boiler Reactor in low- and high-power configurations (LOPO and HYPO), and Omega West] 

until 1967. After that time, LANL monitored 41Ar emissions until the reactors ceased operation. In 

1973, LANL reported 133Xe and 135Xe emissions, but it was at a combined rate less than that of 41Ar. 

Because dose coefficients for xenon isotopes are 3 to 5 times less than that for 41Ar, estimated doses 

for xenon isotopes are insignificant in relation to the 41Ar doses.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 23 of 96

Only 41Ar is listed consistently in the source emissions for this TA. The annual average air 

concentrations of 41Ar listed in Table C-28 of Attachment C for TA-2 were calculated using 

screening-level models from NCRP (1996). Because there was no mention of a stack in association 

with TA-2 in the early years, this analysis assumed that releases and receptors were at essentially the 

same height for all years. 

To calculate average annual air concentrations using the emissions data in Table A-2, this analysis 

used the following model (NCRP 1996, p. 12):

χ/Q = fB/u s/m3 (4-2)

where:

χ = concentration at receptor (Ci/m3

)

Q = stack or building vent release rate (Ci/s)

f = wind frequency

B = Gaussian plume model diffusion factor modified for building wake effects (1/m2

)

u = wind speed (m/s)

The value for the independent factor f corresponds to the default of 0.25 (the maximum frequency for 

any compass point) from NCRP (1996), and the site-specific value for u is 2.8 m/s (LANL 1994, 1999). 

The value for B of 2 × 10-4 is from Figure 2.3 in NCRP (1996) for a distance of 500 m. This is the 

average distance a receptor was assumed to be from the release point. This B value was the largest 

value for this receptor distance for any projected cross-sectional frontal area (AG) of the building that 

influenced airflow. The resultant average χ/Q was 1.8 × 10-5 s/m3

.

The analysis calculated average annual doses from these concentrations by assuming an individual 

was exposed to this air concentration for 2,000 hr/yr. The analysis used dose coefficients for skin and 

whole body from the Federal Guidance Report No. 12 (Eckerman and Ryman 1993). The dose 

coefficient for skin is 3.74 × 10-6 mrem per μCi-s/m3 (1.01 × 10-13 Sv per Bq-s/m3

) and for whole body 

is 2.41 × 10-6 mrem per μCi-s/m3 (6.50 × 10-14 Sv per Bq-s/m3

). For pre-1967 years, exposures to 

noble gases in TA-2 could be estimated from area badge data (which has not been found at this time) 

or by assuming that the annual dose for 2,000-hr/yr exposure is the peak average annual dose in 

Table 4-26. 

4.3.2.2 Los Alamos Neutron Science Center (TA-53)

The large, high-current accelerator at TA-53 began operation in 1976. Since then, this facility 

released megacurie quantities of activation products annually through the exhaust stack. In addition 

to 41Ar, the accelerator stack released significant activities of 11C, 13N, and 15O. While not noble 

gases, these three nuclides have extremely short half-lives and cause radiation exposure more like 

noble gases than long-lived particulates. Therefore, this discussion considers emissions for all these 

radionuclides. 

After 1981, emissions were often reported as gaseous/mixed activation products (G/MAPs) without 

differentiating the radionuclides in that category. Submersion dose coefficients for the four 

radionuclides (11C, 13N, 15O, and 41Ar) are less than or equal to the skin dose factor for 15O 

(1.04 × 10-13 Sv/Bq or 3.85 × 10-6 mrem/μCi) or the whole-body dose factor for 41Ar (6.50 × 10-14 Sv/Bq 

or 2.41 × 10-6 mrem/μCi) according to Federal Guidance Report No. 11 (Eckerman, Wolbarst, and 

Richardson 1988). Therefore, this analysis simplified the calculations by assuming that the composite 

emissions activity for all four radionuclides was equal to that for 15O alone for skin dose, and to that for 

41Ar alone for whole-body dose.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 24 of 96

To estimate air concentrations from the LANSCE stack, the analysis considered three work locations: 

TA-53, TA-21, and TA-72. TA-53 was the location where the accelerator operated. The two nearby 

locations were the east end of TA-21 (DP East; 2,000 m south-southeast of TA-53) and the west end 

of TA-72 (on East Jemez Road; 700 m south-southeast of TA-53). An average wind rose for each of 

five meteorological stations at LANL, which are discussed in the 1999 Site-Wide Environmental 

Impact Statement for LANL (DOE 1999), indicates that the predominant wind directions from TA-53 

are to the north and northeast (Figure 4-3).

For TA-53, this analysis used the same approach that was adopted for TA-2 to estimate average air 

concentrations. Again, this assumed no stack release and resulted in an average χ/Q of 

1.8 × 10-5 s/m3 (receptor 500 m from the emission point).

Bowen (1987) modeled dispersion from the LANSCE stack using Gaussian equations. However, the 

calculations were for a receptor at the site boundary (East Gate) rather than for onsite work locations. 

The East Gate is approximately 800 m east of TA-53. The dispersion factor from this modeling effort 

was adjusted for this work to apply to TA-21 and TA-72 to develop average annual concentrations. 

The adjustment was based on distances from TA-53, and differential wind frequencies were ignored. 

Wind frequencies toward both TA-21 and TA-72, as measured at the East Gate, are 3%, which is 

consistent with Figure 4-3. The wind frequency toward the public receptor is 13%. Therefore, the 

assumption that wind frequency is 13% (i.e., not adjusting the dispersion factor based on wind 

frequencies) is an approach more favorable to the claimant. 

The calculated χ/Q for the East Gate receptor (800 m from TA-53) was 3.8 × 10-6 s/m3 (Bowen 1987). 

Because TA-72 is approximately the same distance (700 m) from TA-53 as the East Gate, this χ/Q

was used to estimate average annual air concentrations at this location. This value of χ/Q was 

adjusted to account for the increased distance of TA-21 from TA-53 (2,000 m) by multiplying the χ/Q

for the East Gate by a factor of one-third. The factor of one-third was derived by comparing the 

Gaussian plume model diffusion factor P in NCRP (1996, Figure 2.2) for a 30-m stack and the two 

different distances (800 m and 2,000 m). The resultant estimate of χ/Q is approximately 

1.3 × 10-6 s/m3

. This information is summarized below. 

Receptor

Distance/direction

from TA-53

Average X/Q

(s/m3)

East Gate 800m/East 3.8 E-06

TA-21 2,000m/SSE 1.3 E-06

TA-72 700m/SSE 3.8 E-06

Table C-29 of Attachment C lists the results of these calculations for TA-53, TA-21, and TA-72.

This analysis calculated estimates of external dose (skin and whole body) from LANSCE emissions 

for TA-53, TA-21, and TA-72. The estimated doses in Tables 4-29 and 4-30 are based on average 

annual air concentrations in TA-53, TA-21, and TA-72 from Table C-29. The concentrations at TA-53 

assumed a ground-level release. Therefore, the air concentration estimates for TA-53 account for the 

fact that a percentage of the emissions from that location was diffuse, rather than from the 30-m 

stack. 

4.4 UNCERTAINTY

As discussed in previous sections, estimates of annual intakes employed conservative assumptions 

when information was lacking. Due to the lack of information on particle size and solubility, this 

analysis compensated for the uncertainty of these elements by assuming that all effluents were in the 

respirable size range and by selecting solubility based on the highest dose rate. 
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 25 of 96

Figure 4-3. Average wind rose for five meteorological stations (DOE 1999).
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 26 of 96

Effluent data for 1971 and later have an estimated uncertainty of ±20%. Data from earlier years are 

much less accurate because of less reliable measurement technology and less stringent reporting 

requirements. As stated elsewhere, the pre-1971 period is included in the SEC period for the LANL 

and it is not necessary to estimate environmental internal doses for the purpose of partial dose 

reconstruction in the early years.

The accuracy of the area badge data is also about ±20%. However, subtraction of background from 

these measurements adds more uncertainty because of the variability and selection of background 

information.

Table 4-1. Estimated annual average intakes of 

241Am, 3

H, 239Pu, and 234U for TA-2 (Bq/yr).a

Year Am-241 H-3b Pu-239 U-234

1971 3.1E-04c 3.5E-03c

1972 3.1E-04c 3.5E-03c

1973 3.1E-04c 3.5E-03c

1974 3.1E-04c 3.5E-03c

1975 3.1E-04c 3.5E-03c

1976 3.1E-04c 3.5E-03c

1977 3.1E-04c 3.5E-03c

1978 3.1E-04c 3.5E-03c

1979 3.1E-04c 3.5E-03c

1980 3.1E-04c 3.5E-03c

1981 3.1E-04c 3.5E-03c

1982 3.1E-04c 3.5E-03c

1983 3.1E-04c 3.5E-03c

1984 3.1E-04c 3.5E-03c

1985 3.1E-04c 3.5E-03c

1986 3.1E-04c 3.5E-03c

1987 3.6E+03 8.9E-05 4.7E-03

1988 1.0E+04 2.0E-03 6.3E-03

1989 3.0E+03 2.0E-04 8.9E-03

1990 1.5E+03 1.2E-04 3.2E-03

1991 6.9E+02 4.4E-05 6.6E-03

1992 5.7E+02 1.3E-04 3.3E-03

1993 3.3E+02 5.7E-04 2.4E-03

1994 5.6E+02 2.8E-04 1.5E-03

1995 4.6E-04 4.5E+02 5.5E-04 3.7E-03

1996 5.2E+02c 3.1E-04c 3.5E-03c

1997 5.2E+02c 3.1E-04c 3.5E-03c

1998 5.2E+02c 3.1E-04c 3.5E-03c

1999 5.2E+02c 3.1E-04c 3.5E-03c

2000 0.0E+00 2.4E+02 1.3E-04 1.6E-03

2001 2.4E+02d 1.3E-04d 1.6E-03d

2002 2.4E+02d 1.3E-04d 1.6E-03d

2003 2.4E+02d 1.3E-04d 1.6E-03d

a. Calculated from estimated air concentrations in Table C-2, 

assuming an inhalation rate of 2,400 m3

/yr (and multiplying by 

3.7 × 10-2 Bq/pCi); blanks indicate no data are available for 

those years. 

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. Estimated from average of values from 1991 to 1995.

d. Assumed to be the same as value in 2000.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 27 of 96

Table 4-2. Estimated annual average intakes of 241Am, 3H, 239Pu, 232Th, 234U, MFP, 

and P/VAP for TA-3 (Bq/yr).a

Year Am-241 H-3b Pu-239 Th-232 U-234 MFPc P/VAPd

1971 2.7E+04 2.5E-02 2.3E-02

1972 2.8E-03 4.4E+03 1.2E-02 6.9E-03

1973 6.2E-04 4.7E+03 1.2E-02 3.0E-03 1.4E-02 2.5E+00

1974 2.9E-01 3.9E-02 6.7E-02

1975 6.4E+03 8.2E-02 3.8E-02 3.6E-02

1976 7.7E-03 7.1E-02 8.1E-02

1977 1.2E+05 6.5E-03 6.6E-02 9.4E-02

1978 2.9E+04 1.1E-02 3.6E-02 7.9E-02

1979 8.8E+05 2.1E-01 5.1E-02 9.2E-02

1980 1.3E+03 1.4E-01 3.0E-02 8.3E-02

1981 2.6E+05 7.7E-03 4.6E-02 3.4E-02

1982 5.7E+05 1.5E-02 6.3E-02 1.5E-02

1983 6.7E+05 1.7E-02 3.5E-02 3.3E-03

1984 5.2E+05 2.2E-02 4.2E-02 8.1E-03

1985 6.2E+05 3.8E-02 6.7E-02 6.8E-03

1986 3.6E+05 3.8E-02 1.2E-01 9.4E-03

1987 2.5E+05 1.3E-02 1.7E-01 4.2E-03

1988 2.4E+06 1.0E-02 9.8E-02 5.8E-03

1989 8.5E+04 7.6E-03 7.1E-02 7.5E-03

1990 1.5E+05 4.2E-03 3.8E-02 7.6E-03

1991 1.3E-04 2.0E+03 1.1E-04 8.2E-03 2.8E-03

1992 2.8E-04 3.6E+03 2.2E-04 3.2E-03 1.6E-03

1993 1.7E-03 7.1E+02 4.9E-03 1.3E-03 1.2E-03

1994 5.2E-04 2.7E+02 2.8E-04 3.3E-03 7.5E-03

1995 1.3E-03 8.0E+02 2.6E-04 1.8E-03 1.8E-01 4.4E+02

1996 1.3E-04 1.7E+02 2.4E-04 3.2E-05 2.1E-03

1997 2.2E-04 4.8E+02 2.4E-04 7.4E-05 1.5E-03

1998 3.1E-04 3.6E+02 3.6E-05 8.2E-05 1.3E-03 3.1E+00

1999 2.0E-04 3.6E+02 2.4E-04 4.3E-05 1.7E-03

2000 0.0E+00 3.2E+02 2.3E-04 2.5E-05 2.7E-03

2001 0.0E+00 4.1E+02 5.3E-05 2.7E-05 2.4E-03

2002 1.5E-04e 3.4E+02 1.6E-04 5.0E-05 1.9E-03

2003 1.5E-04e 3.9E+02 1.6E-04 5.0E-05 1.9E-03

a. Calculated from estimated air concentrations in Table C-3, assuming an inhalation rate of 2,400 

m3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no data are available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. It is favorable to the claimant to assume all is 90Sr.

d. It is favorable to the claimant to assume all is 68Ge, Type M.

e. Estimated from average of corresponding values for 1997 to 2001.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 28 of 96

Table 4-3. Estimated annual average intakes of 241Am, 3H, 

239Pu, and 234U for TA-5 (Bq/yr).a

Year Am-241 H-3b Pu-239 U-234

1971

1972

1973 1.4E+04 1.7E-03 4.1E-02

1974 1.1E+04 2.2E-03 1.4E-02

1975 2.3E+04 1.9E-03 9.9E-03

1976 1.6E+04 4.4E-04 8.4E-03

1977 7.6E+03 1.9E-03 1.1E-02

1978 2.1E+03 2.6E-03 8.4E-03

1979 2.0E+03 7.5E-04 1.1E-02

1980 2.3E+03 8.9E-05 7.7E-03

1981 5.9E+02 5.4E-04 5.8E-03

1982 3.3E+03 1.3E-04 5.8E-03

1983 2.3E+03 2.8E-04 6.6E-03

1984 2.4E+03 1.2E-04 5.1E-03

1985 1.7E+03 0.0E+00 4.5E-03

1986 1.3E+03 8.9E-05 3.7E-03

1987 2.6E+03 1.8E-05 5.4E-03

1988 2.0E+03 1.8E-05 9.7E-03

1989 4.7E+02 3.6E-05 1.1E-02

1990 4.3E+02 1.6E-04 4.4E-03

1991 4.9E+02 6.2E-05 7.6E-03

1992 1.2E-04 5.9E+02 7.1E-05 3.0E-03

1993 3.5E+02 1.3E-04 3.1E-03

1994 2.0E+02 1.1E-04 3.1E-03

1995 3.0E-04 3.2E+02 3.9E-04 4.2E-03

1996 2.2E-04 1.5E+02 1.1E-04 5.0E-03

1997 2.1E-04 7.3E+02 4.4E-05 2.2E-03

1998 1.8E-04 4.4E+03 8.9E-05 2.1E-03

1999 3.2E-04 2.9E+02 1.8E-05 1.9E-03

2000 2.7E-05 3.6E+02 1.8E-04 4.8E-03

2001 0.0E+00 5.6E+02 0.0E+00 3.0E-03

2002 1.5E-04c 1.3E+03c 6.6E-05c 2.8E-03c

2003 1.5E-04c 1.3E+03c 6.6E-05c 2.8E-03c

a. Calculated from estimated air concentrations in Table C-4,

assuming an inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 

× 10-2 Bq/pCi); blanks indicate no data are available for those 

years. 

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. Estimated from average of corresponding values for 1997 to 2001.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 29 of 96

Table 4-4. Estimated annual average intakes of 241Am, 3H, 

239Pu, and 234U for TA-6 (Bq/yr).a

Year Am-241 H-3b Pu-239 U-234

1971 4.8E+03 3.6E-03 3.3E-02

1972 3.9E+03 1.3E-02 8.3E-03

1973

1974 2.1E+03 2.3E-03 6.9E-03

1975 9.8E-04 2.9E+03 4.8E-03 3.7E-03

1976 3.3E+03 3.5E-04 8.1E-03

1977 2.7E-05 3.3E+03 1.5E-03 2.3E-02

1978 2.7E-05 6.7E+02 2.4E-03 9.9E-03

1979 0.0E+00 3.7E+02 2.9E-04 4.5E-03

1980 8.9E-06 5.1E+02 2.3E-04 3.9E-03

1981 4.0E-03 8.9E+02 5.1E-04 4.4E-03

1982 1.8E-05 1.5E+03 1.1E-04 4.3E-03

1983 1.5E+03 1.1E-04 4.7E-03

1984 5.9E+02 1.1E-04 2.8E-03

1985 1.1E+03 1.7E-04 5.3E-03

1986 2.8E-04 4.8E+02 1.1E-04 5.1E-03

1987 1.3E-04 1.5E+03 5.3E-05 5.5E-03

1988 5.7E-04 1.3E+03 6.2E-05 7.2E-03

1989 2.5E-04 3.1E+02 4.1E-04 9.0E-03

1990 1.4E-04 1.9E+02 1.9E-04 6.4E-03

1991 8.0E-05 2.1E+02 8.9E-05 7.4E-03

1992 4.0E-04 3.6E+02 1.5E-04 2.4E-03

1993 1.3E-04 4.4E+02 2.0E-04 2.0E-03

1994 3.6E-04 1.7E+02 7.1E-05 2.5E-03

1995 5.1E-04 4.8E+02 1.1E-03 1.8E-03

1996 0.0E+00

1997–2003

a. Calculated from estimated air concentrations in Table C-5 assuming 

an inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 × 10-2

Bq/pCi); blanks indicate no data are available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

Table 4-5. Estimated annual average 

intakes of 3

H for TA-9 (Bq/yr).

a

Year H-3b

1971

1972 2.1E+05

1973 1.1E+04

1974 3.8E+02

1975

1976 3.8E+04

1977 7.6E+03

1978 7.6E+02

1979 1.5E+03

1980 1.5E+03

1981–2003

a. Calculated from estimated air concentrations in 

Table C-6 assuming an inhalation rate of 2,400 

m3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); 

blanks indicate no data are available for those 

years. 

b. 3

H intake multiplied by 1.5 to account for 

submersion dose.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 30 of 96

Table 4-6. Estimated annual average intakes of 241Am, 3H, 

239Pu, and 234U for TA-11 (Bq/yr).a

Year Am-241 H-3b Pu-239 U-234

1971 5.6E+03 4.2E-03 1.2E-02

1972 2.9E-03 3.2E+03 4.3E-03 8.3E-03

1973 1.7E+03 2.0E-03 1.4E-02

1974–2003

a. Calculated from estimated air concentrations in Table C-8 

assuming an inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 × 

10-2 Bq/pCi); blanks indicate no data are available for those 

years. 

b. 3H intake multiplied by 1.5 to account for submersion dose.

Table 4-7. Estimated annual average intakes of 241Am, 3H, 

239Pu, and 234U for TA-15 (Bq/yr).a

Year Am-241 H-3b Pu-239 U-234

1971 1.1E+04 3.7E-03 6.2E-02

1972 2.0E-03 3.7E+03 4.5E-03 8.3E-03

1973 1.8E-04 2.8E+03 1.4E-03 2.8E-02

1974–1977

1978 2.1E+04

1979–1991

1992 4.5E-01

1993 1.4E+02 9.7E-01

1994 2.6E+02 3.6E-05 5.9E-03

1995 4.5E-04 2.3E+02 3.3E-04 1.3E-03

1996 2.0E-04 1.5E+02 1.2E-04 4.6E-03

1997 1.7E-04 2.5E+02 5.8E-05 2.6E-03

1998 1.9E-04 2.7E+02 7.1E-05 1.3E-03

1999 2.0E-04 2.3E+02 7.1E-05 1.7E-03

2000 3.6E-05 2.4E+02 4.4E-06 2.4E-03

2001 2.2E-04 3.1E+02 0.0E+00 5.8E-03

2002 1.8E-06 3.7E+02 0.0E+00 3.4E-03

2003 1.3E-04c 2.8E+02c 2.9E-05c 2.9E-03c

a. Calculated from estimated air concentrations in Table C-9, assuming 

an inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 × 10-2

Bq/pCi; blanks indicate no data are available for those years).

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. Estimated from average of corresponding values for 1998 to 2002.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 31 of 96

Table 4-8. Estimated annual average intakes of 241Am, 3H, 

239Pu, and 234U for TA-16 (Bq/yr).a

Year Am-241 H-3b Pu-239 U-234

1971 6.0E+03 5.4E-03 2.8E-02

1972 3.6E-03 4.1E+03 5.1E-03 8.3E-03

1973 2.7E-04 2.1E+03 2.5E-03 1.4E-02

1974 1.6E+03 2.7E-03 9.6E-03

1975 3.6E-04 2.4E+03 1.7E-03 3.6E-03

1976 2.7E+03 4.2E-04 4.8E-03

1977 0.0E+00 4.0E+03 1.7E-03 3.8E-02

1978 0.0E+00 8.0E+02 3.2E-03 6.6E-03

1979 0.0E+00 2.9E+02 1.8E-03 3.6E-03

1980 0.0E+00 1.5E+03 9.8E-05 4.1E-03

1981 1.7E-04 2.5E+02 3.2E-04 3.2E-03

1982 2.7E-05 1.3E+03 8.9E-05 3.2E-03

1983 1.5E+03 4.9E-05 3.2E-03

1984 1.7E+03 0.0E+00 1.8E-03

1985 1.3E+03 3.5E-04 3.8E-03

1986 2.4E-04 6.3E+02 5.3E-05 1.8E-03

1987 8.9E-05 1.3E+03 6.7E-05 2.6E-03

1988 1.7E-04 5.7E+02 7.5E-05 4.7E-03

1989 2.1E-04 3.5E+02 5.3E-05 8.1E-03

1990 2.5E-04 1.5E+02 1.4E-04 4.6E-03

1991 1.1E-04 6.7E+01 8.9E-05 5.4E-03

1992 9.8E-05 2.1E+02 5.3E-04 2.5E-03

1993 1.2E+02 4.4E-05 1.7E-03

1994 1.2E+03 0.0E+00 2.3E-03

1995 4.1E-04 2.4E+04 2.9E-04 1.7E-03

1996 1.6E-04 3.2E+03 3.6E-05 2.4E-03

1997 2.0E-04 8.3E+03 7.1E-05 1.7E-03

1998 2.3E-04 3.3E+04 8.0E-05 2.6E-03

1999 2.8E-04 7.3E+03 1.1E-04 1.3E-03

2000 0.0E+00 8.1E+03 0.0E+00 1.3E-03

2001 1.8E-05 9.1E+03 0.0E+00 1.7E-03

2002 1.5E-04c 1.3E+04c 5.2E-05c 1.7E-03c

2003 1.5E-04c 1.3E+04c 5.2E-05c 1.7E-03c

a. Calculated from estimated air concentrations in Table C-10, 

assuming an inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 × 

10-2 Bq/pCi); blanks indicate no data are available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. Estimated from average of corresponding values for 1997 to 2001.

Table 4-9. Estimated annual average 

intakes of 234U for TA-18 (pCi/yr).

a

Year U-234

1971–1978

1979 7.7E-04

1980–2003

a. Calculated from estimated air concentrations 

in Table C-11, assuming an inhalation rate of 

2,400 m3

/yr (and multiplying by 3.7 × 10-2

Bq/pCi; blanks indicate no data are available 

for those years).
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 32 of 96

Table 4-10. Estimated annual average intakes of 241Am, 3H, 

239Pu, 234U, and MFP for TA-21 (Bq/yr).a

Year Am-241 H-3b Pu-239 U-234 MFPc

1971 5.7E-04d 1.1E+04 2.6E-03 1.1E-02

1972 5.7E-04d 2.0E+04e 7.5E-03 9.6E-03

1973 5.7E-04d 2.0E+04 2.0E-03 1.4E-02 2.0E-04

1974 5.7E-04d 2.0E+04e 2.1E-03 6.9E-03 5.7E-04

1975 5.7E-04d 8.5E+03 1.6E-03 4.3E-03 2.8E-04

1976 5.7E-04d 5.3E+03 6.7E-04 5.8E-03 1.1E-04

1977 5.7E-04d 6.9E+03 1.9E-03 1.3E-02 6.4E-04

1978 6.6E-06 6.9E+03e 2.0E-03 1.3E-02 2.0E-04

1979 3.7E-06 5.1E+02 5.4E-04 1.1E-02 9.1E-05

1980 1.2E-05 1.5E+03 2.8E-03 9.9E-03 8.2E-04

1981 5.7E-06 7.5E+02 4.1E-04 5.0E-03 5.5E-04

1982 6.8E-06 2.1E+03 5.3E-04 1.3E-02 8.5E-05

1983 1.9E-05 2.7E+03 8.0E-05 4.3E-03 1.6E-04

1984 5.7E-04d 1.2E+03 1.3E-04 8.9E-03 6.1E-05

1985 5.7E-04d 2.1E+03 3.6E-05 5.8E-03 7.1E-05

1986 5.7E-04d 2.2E+03 1.2E-04 4.8E-03 6.3E-05

1987 5.7E-04d 6.9E+03 9.8E-05 4.8E-03 3.7E-05

1988 5.7E-04d 5.3E+03 7.1E-05 7.2E-03 3.0E-05

1989 5.7E-04d 2.2E+03 1.2E-04 1.1E-02 6.1E-06

1990 5.7E-04d 1.7E+03 2.0E-04 6.7E-03 2.5E-06

1991 0.0E+00 1.1E+03 1.7E-04 7.5E-03 5.9E-06

1992 2.4E-04 1.2E+03 2.2E-04 3.3E-03 4.7E-06

1993 3.2E-04 5.6E+02 4.4E-04 2.4E-03 2.0E-06

1994 5.7E-04 4.5E+02 5.9E-04 2.5E-03 9.8E-06

1995 5.5E-04 1.1E+03 1.1E-03 2.8E-03

1996 3.7E-04 4.1E+02 1.5E-03 2.2E-02

1997 3.8E-04 6.3E+02 1.5E-03 1.9E-03

1998 5.0E-04 1.5E+03 2.3E-03 1.4E-03

1999 2.6E-04 8.2E+02 3.1E-04 1.9E-03

2000 8.3E-05 9.7E+02 3.3E-04 1.8E-03

2001 0.0E+00 9.6E+02 3.3E-04 2.3E-03

2002 2.4E-04f 9.8E+02f 9.5E-04f 1.9E-03f

2003 2.4E-04f 9.8E+02f 9.5E-04f 1.9E-03f

a. Calculated from estimated air concentrations in Table C-12, assuming an 

inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks 

indicate no data are available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. MFP = mixed fission products; favorable to the claimant to assume all is 

90Sr.

d. Assumed to be the highest value of all years for which data are available.

e. Assumed to be the highest value of the two adjacent years.

f. Estimated from average of corresponding values for 1997 to 2001.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 33 of 96

Table 4-11. Estimated annual average intakes of 241Am, 

3

H, 239Pu, and 234U for TA-33 (Bq/yr).

a

Year Am-241 H-3b Pu-239 U-234

1971 6.6E+04 7.4E-03 1.1E-02

1972 2.4E+04 4.9E-03 1.2E-02

1973 8.0E+03 1.5E-03 2.8E-02

1974 1.9E+04 2.5E-03 9.6E-03

1975 2.1E+04 2.0E-03 3.4E-03

1976 7.9E+03 4.7E-04 5.6E-03

1977 1.1E+03 1.6E-03 1.1E-02

1978 3.3E+03 2.5E-03 8.4E-03

1979 5.3E+03 6.1E-04 5.4E-03

1980 5.9E+03 3.1E-04 6.2E-03

1981 4.0E+03 3.5E-04 5.0E-03

1982 1.2E+04 2.1E-04 5.1E-03

1983 4.8E+03 0.0E+00 2.9E-03

1984 7.5E+03 6.2E-04 2.5E-03

1985 1.4E+04 0.0E+00 2.7E-03

1986 4.2E+03 5.3E-05 2.0E-03

1987 2.6E+03 7.1E-05 4.5E-03

1988 7.7E+03 3.6E-05 1.3E-02

1989 2.4E+03 0.0E+00 7.3E-03

1990 1.1E+03 6.5E-04 7.7E-03

1991 4.3E+02 6.2E-05 1.7E-03

1992 4.9E+02 8.0E-05 1.3E-03

1993 4.0E+02 1.6E-04 1.4E-03

1994 2.4E+02 4.4E-05 1.3E-03

1995 3.5E-04 4.7E+02 1.4E-03 1.5E-03

1996 3.5E-04c 1.9E+02 1.4E-03c 1.5E-03c

1997 2.8E-04 1.2E+02 1.2E-04 1.2E-03

1998 2.1E-04 1.7E+02 1.2E-04 1.4E-03

1999 2.2E-04 5.3E+02 1.1E-04 1.8E-03

2000 0.0E+00 4.5E+02 1.8E-05 9.9E-04

2001 4.4E+02 0.0E+00 1.3E-03

2002 3.4E+02d 7.5E-05d 1.3E-03d

2003 3.4E+02d 7.5E-05d 1.3E-03d

a. Calculated from estimated air concentrations in Table C-13, 

assuming an inhalation rate of 2,400 m3

/yr (and multiplying by 

3.7 × 10-2 Bq/pCi); blanks indicate no data are available for 

those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. Assumed to be the highest value of the two adjacent years.

d. Estimated from average of corresponding values for 1997 to 

2001.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 34 of 96

Table 4-12. Estimated annual average intakes of 241Am, 3H, 239Pu, 234U, 

MFP, and P/VAP for TA-35 (Bq /yr).

a

Year Am-241 H-3b Pu-239 U-234 MFPc P/VAPd

1971 9.2E+05 1.4E-03

1972 7.3E+05 3.5E-03

1973 3.6E+05 4.6E-04

1974 4.1E+05 1.6E-03

1975 7.0E+05 1.2E-03

1976 4.9E+05 4.6E-04

1977 2.3E+05 1.6E-04

1978 2.0E+05 3.8E-04

1979 3.8E+05 1.4E-03

1980 7.3E+03 4.0E-05

1981 9.2E+05e 5.2E-05

1982 9.2E+05e 2.5E-04

1983 1.8E+03 1.8E-04

1984 6.0E+04 8.1E-05

1985 1.5E+03 1.1E-04

1986 1.4E+04 7.1E-05

1987 4.5E+04 1.2E-04

1988 3.5E+04 3.4E-05

1989 5.3E+03 1.3E-04

1990 1.2E+01 1.7E-04

1991 1.3E-03 2.4E-04

1992 2.9E+01 7.0E-05

1993 5.3E-05

1994 7.6E-05

1995 6.9E-06 5.8E-05 1.4E-04 3.2E-04 3.2E-04

1996–2003

a. Calculated from estimated air concentrations in Table C-14, assuming an inhalation rate 

of 2,400 m3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no data are 

available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. It is favorable to the claimant to assume all is 90Sr.

d. It is favorable to the claimant to assume all is 68Ge, Type M.

e. Assume highest average value for 3

H in 1981 and 1982; there are no source terms or 

environmental data readily available.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 35 of 96

Table 4-13. Estimated annual average intakes of 241Am, 

3

H, 239Pu, and 234U for TA-36 (Bq/yr).a

Year Am-241 H-3b Pu-239 U-234

1971 5.1E+03 2.4E-03 7.8E-02

1972 3.9E+03 5.1E-03 8.3E-03

1973 3.9E+03 2.0E-03 1.4E-02

1974–1992

1993 1.5E+02

1994 1.7E+02 1.0E-03 6.2E-03

1995 4.1E-04 4.9E+02 1.0E-03 8.0E-03

1996 1.3E-04 1.5E+02 7.1E-05 4.3E-03

1997 1.8E-04 1.8E+02 5.8E-05 3.4E-03

1998 1.9E-04 2.4E+02 2.2E-05 3.1E-03

1999 3.2E-04 2.3E+02 4.0E-05 3.1E-03

2000 4.4E-05 2.1E+02 1.3E-05 2.9E-03

2001 0.0E+00 3.3E+02 0.0E+00 1.4E-02

2002 1.8E-06 3.7E+02 0.0E+00 3.4E-03

2003 1.1E-04c 2.8E+02c 1.5E-05c 5.2E-03c

a. Calculated from estimated air concentrations in Table C-15, 

assuming an inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 × 

10-2 Bq/pCi); blanks indicate no data are available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. Estimated from average of corresponding values for 1998 to 2002.

Table 4-14. Estimated annual average intakes of 

3

H, 239Pu, and 234U for TA-39 (Bq/yr).a

Year H-3b Pu-239 U-234

1971 1.7E+01

1972 2.1E+01

1973–1976

1977 5.2E+03 8.9E-06 1.1E-02

1978 2.0E+03 3.1E-03 1.1E-02

1979 2.1E+03 3.3E-04 3.6E-03

1980 3.7E+03 3.9E-04 6.5E-03

1981 1.6E+03 1.8E-04 4.3E-03

1982 2.0E+04 2.4E-04 7.4E-03

1983 4.1E+03 1.6E-04 1.4E-03

1984 1.9E+03 0.0E+00 3.2E-03

1985 5.5E+03 0.0E+00 4.6E-03

1986 3.3E+03 1.3E-04 2.7E-03

1987–2003

a. Calculated from estimated air concentrations in Table C16, assuming an inhalation rate of 2,400 m3

/yr (and 

multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no data 

are available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 36 of 96

Table 4-15. Estimated annual average intakes of 3H, 239Pu, 

and 234U for TA-41 (Bq/yr).

a

Year H-3b Pu-239 U-234

1971 9.4E+04 3.7E-03

1972 3.2E+04 2.1E-03

1973 1.7E+04 3.0E-04

1974–1978

1979 4.2E+04

1980 1.2E+05

1981 3.7E+04

1982 3.8E+04

1983 2.9E+05

1984 1.4E+06

1985 3.7E+05

1986 3.9E+05

1987 1.4E+05

1988 5.1E+05

1989 3.4E+06

1990 1.3E+06

1991 1.1E+06

1992 8.6E+04

1993 1.4E+05 2.0E-06

1994 5.0E+04 3.9E-06

1995 2.3E+04 3.0E-06 1.8E-06

1996 3.2E+04

1997 1.2E+04

1998 1.1E+04

1999 3.8E+03

2000 1.8E+03

2001 1.6E+05

2002 3.7E+04c

2003 3.7E+04c

a. Calculated from estimated air concentrations in Table C-17, 

assuming an inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 × 

10-2 Bq/pCi); blanks indicate no data are available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. Estimated from average of corresponding values for 1997 to 2001.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 37 of 96

Table 4-16. Estimated annual average intakes of 241Am, 3H, 

239Pu, and 234U for TA-43 (Bq/yr).a

Year Am-241 H-3b Pu-239 U-234

1971 5.7E+03 9.8E-03 1.9E-02

1972 3.7E+03 8.9E-03 8.3E-03

1973 1.9E+03 4.6E-03 1.4E-02

1974 1.3E-03

1975 3.2E-04

1976 1.5E-03

1977 9.1E-04

1978 3.0E-04

1979 1.5E-04

1980 3.6E-05

1981 7.2E-05

1982 2.7E-04

1983 6.5E-04

1984 2.1E-04

1985 3.5E-04

1986 5.7E-04

1987 9.9E-05

1988 2.9E-04

1989–1994

1995 5.3E-05 1.0E-04 2.2E-04

1996–2003

a. Calculated from estimated air concentrations in Table C-19, assuming an 

inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); 

blanks indicate no data are available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

Table 4-17. Estimated annual average intakes 

of 234U for TA-46 (Bq/yr).

a

Year U-234

1971 7.8E-04

1972 2.3E-02

1973 4.2E-04

1974 8.0E-05

1975 1.0E-04

1976 6.1E-05

1977 7.8E-07

1978 4.9E-03

1979 4.4E-04

1980 2.9E-04

1981 2.7E-03

1982 4.0E-04

1983 7.0E-06

1984 1.0E-05

1985 5.5E-06

1986 7.8E-07

1987–2003

a. Calculated from estimated air concentrations in Table 

C-20, assuming an inhalation rate of 2,400 m3

/yr (and 

multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no 

data are available for those years.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 38 of 96

Table 4-18. Estimated annual average intakes of 241Am, 239Pu, 

234U, MFP, and P/VAP for TA-48 (Bq/yr).a

Year Am-241 Pu-239 U-234 MFPb P/VAPc

1971 3.7E-03

1972 2.2E-02 1.6E-03

1973 3.9E-03 3.8E-04 2.0E-01

1974 4.7E-03 2.5E-04 1.8E-01

1975 2.4E-03 6.7E-04 1.4E-01

1976 9.8E-04 2.2E-02 2.4E-01

1977 1.6E-03 1.1E-02 4.3E-01

1978 3.7E-04 2.2E-03 2.3E-01

1979 6.6E-05 2.1E-03 2.1E-01

1980 3.1E-04 1.3E-04 3.4E-01

1981 2.6E-04 4.5E-04 2.7E-01

1982 1.9E-03 1.4E-03 2.1E-01

1983 6.4E-04 1.0E-04 1.6E-01

1984 5.0E-04 2.6E-04 3.1E-01

1985 4.0E-04 3.7E-04 2.4E-01

1986 5.6E-04 1.2E-04 4.9E-01

1987 1.2E-04 3.1E-04 2.4E-01

1988 1.4E-04 4.3E-05 2.2E-01

1989 2.9E-04 5.3E-05 8.5E+01

1990 2.9E-04 3.3E-05 2.0E-01

1991 1.1E-04 2.1E-01 2.0E+01

1992 1.3E-03 8.1E-05 5.4E-01 7.4E+00

1993 6.2E-04 2.8E-04 2.6E-01 1.5E+01

1994 6.3E-04 7.8E-05 7.6E-02 1.6E+01

1995 3.3E-04 6.1E-04 1.0E-04 5.2E+00 5.2E+00

1996 9.8E-07 2.1E-06 2.0E-02

1997 7.0E-08 4.9E-07 2.7E-05 3.5E-01

1998 7.2E-08 2.1E-02

1999 1.2E-07 7.6E-01

2000 3.3E+00

2001 4.5E-01

2002 9.8E-01d

2003 9.8E-01d

a. Calculated from estimated air concentrations in Table C-21, assuming an 

inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks 

indicate no data are available for those years.

b. It is favorable to the claimant to assume all is 90Sr.

c. It is favorable to the claimant to assume all is 68Ge, Type M.

d. Estimated from average of corresponding values for 1997 to 2001.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 39 of 96

Table 4-19. Estimated annual average intakes of 241Am, 3H, 

239Pu, and 234U for TA-49 (Bq/yr).a

Year Am-241 H-3b Pu-239 U-234

1971 5.9E-04c 2.0E+04 7.4E-03 3.3E-02

1972 5.9E-04c 2.8E+03 6.7E-03 1.7E-02

1973 5.9E-04c 4.3E+03 1.7E-03 1.4E-02

1974 5.9E-04c 2.9E+03 2.8E-03 1.2E-02

1975 8.9E-05 2.8E+03 1.9E-03 3.7E-03

1976 5.9E-04c 2.9E+03 3.8E-04 7.4E-03

1977 0.0E+00 1.6E+03 1.4E-03 1.5E-02

1978 0.0E+00 6.7E+02 2.3E-03 8.4E-03

1979 0.0E+00 7.2E+02 4.1E-04 5.6E-03

1980 2.0E-04 2.8E+02 5.7E-04 5.2E-03

1981 8.0E-05 5.9E+02 5.2E-04 4.5E-03

1982 0.0E+00 9.2E+02 1.6E-04 6.6E-03

1983 5.9E-04c 1.5E+03 8.9E-06 8.9E-04

1984 5.9E-04c 1.7E+03 7.1E-05 2.2E-03

1985 5.9E-04c 4.8E+03 4.6E-04 3.5E-03

1986 5.9E-04c 3.3E+02 8.9E-05 2.8E-03

1987 1.1E-04 2.4E+03 5.3E-05 2.8E-03

1988 5.9E-04 1.3E+03 6.2E-05 4.1E-03

1989 5.9E-04c 3.5E+02 0.0E+00 6.1E-03

1990 1.5E-04 1.5E+02 7.1E-05 3.7E-03

1991 9.8E-05 1.2E+02 1.5E-04 3.2E-03

1992 4.4E-05 2.1E+02 1.1E-03 4.5E-03

1993 1.3E-04 3.2E+02 2.5E-04 3.0E-03

1994 4.1E-04 1.9E+02 2.3E-04 1.8E-03

1995 3.0E-04 2.9E+02 2.8E-04 1.7E-03

1996 4.3E-04 2.3E+02 4.6E-04 2.2E-03

1997 1.8E-04 4.7E+02 5.3E-05 7.6E-04

1998 2.8E-04 9.0E+02 1.1E-04 1.6E-03

1999 2.4E-04 4.5E+02 4.0E-05 1.6E-03

2000 1.3E-03 4.7E+02 1.8E-05 1.2E-03

2001 4.9E-04d 5.0E+02d 1.4E-04d 1.5E-03d

2002 4.9E-04d 5.0E+02d 1.4E-04d 1.5E-03d

2003 4.9E-04d 5.0E+02d 1.4E-04d 1.5E-03d

a. Calculated from estimated air concentrations in Table C-22, assuming

an inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); 

blanks indicate no data are available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. Assumed to be the highest value of all years for which data are 

available.

d. Estimated from average of corresponding values for 1996 to 2000.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 40 of 96

Table 4-20. Estimated annual average intakes of 241Am, 3H, 239Pu, 232Th, 

234U, and MFP for TA-50 (Bq/yr).a

Year Am-241 H-3b Pu-239 Th-232 U-234 MFPc

1971 8.4E+04 3.1E-03

1972 5.4E-03

1973 4.9E-04 3.4E-03

1974 7.6E-04 1.9E-02

1975 8.0E-04 8.9E-03

1976 2.1E-04 5.8E-03

1977 1.4E-02 1.8E-02

1978 3.4E-03 8.4E-03

1979 5.7E-04 2.2E-03

1980 2.3E-04 1.7E-03

1981 3.5E-04 5.1E-03

1982 1.3E-03 3.1E-03

1983 1.1E-03 1.9E-03

1984 7.2E-04 1.9E-03

1985 3.9E-04 1.8E-03

1986 5.6E-04 4.2E-03

1987 8.8E-04 4.6E-03

1988 4.0E-04 2.9E-03

1989 9.0E-05 2.1E-03

1990 2.9E-05 8.3E-04

1991 2.7E-04 6.5E-04

1992 1.1E-04 7.5E-04

1993 5.5E-05 7.9E-04

1994 6.1E-05 1.4E-03

1995 1.2E-05 1.4E-04

1996 2.1E-06 8.2E-06 3.7E-05

1997 1.6E-06 1.1E-05 2.5E-07

1998 1.3E-06 2.9E-06 1.5E-05 3.7E-05

1999 2.5E-05 1.0E-05 7.2E-06 3.7E-06

2000 2.7E-05 1.9E-06 1.0E-05

2001 1.1E-08 8.4E-06

2002 1.1E-05d 6.8E-06d

2003 1.1E-05d 6.8E-06d

a. Calculated from estimated air concentrations in Table C-23, assuming an inhalation rate 

of 2,400 m3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no data are 

available for those years.

b. H-3 intake multiplied by 1.5 to account for submersion dose.

c. It is favorable to the claimant to assume all is 90Sr.

d. Estimated from average of corresponding values for 1997 to 2001.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 41 of 96

Table 4-21. Estimated annual average intakes of 241Am, 3H, 239Pu, 

234U, and P/VAP for TA-53 (Bq/yr).a

Year Am-241 H-3b Pu-239 U-234c P/VAPd

1971 1.1E+04 5.9E-03 2.2E-02

1972 3.9E-03 4.4E+03 5.7E-03 9.6E-03

1973 1.8E-04 4.2E+03 2.2E-03 1.4E-02

1974 1.3E+04 2.8E-03 1.5E-02

1975 2.7E-04 9.5E+03 2.0E-03 7.3E-03

1976 6.5E+03 4.4E-04 8.5E-03

1977 1.1E-04 4.7E+03 1.6E-03 1.5E-02

1978 1.7E+03 1.5E-03 5.5E-03

1979 5.7E+02 4.4E-04 1.1E-02

1980 8.0E-05 8.3E+02 6.4E-04 1.1E-02

1981 1.2E-04 7.2E+02 5.6E-04 3.6E-03

1982 8.9E-06 9.7E+02 2.0E-04 7.3E-03 3.6E+04

1981 1.5E+03 8.9E-05 3.4E-03 5.2E+05

1984 1.2E+03 5.3E-05 4.5E-03 4.9E+05

1985 1.6E+03 1.1E-04 3.7E-03 3.9E+01

1986 2.7E-04 1.3E+03 7.1E-05 4.2E-03 2.0E+01

1987 7.1E-05 2.0E+03 3.6E-05 4.2E-03 3.9E+01

1988 1.9E-04 3.2E+03 2.0E-04 7.9E-03 2.0E+01

1989 2.9E-04 4.5E+02 8.9E-05 9.9E-03 2.0E+01

1990 2.0E-04 5.2E+02 2.1E-04 9.7E-03 1.6E+01

1991 6.2E-05 1.5E+02 2.7E-04 5.4E-03 3.9E+01

1992 1.6E-04 6.5E+02 2.2E-04 6.9E-03 1.4E+02

1993 3.3E-04 3.2E+02 1.2E-04 1.7E-03 2.0E+03

1994 3.5E-04 2.5E+02 2.2E-04 1.9E-03 6.1E+01

1995 5.4E-04 3.6E+02 9.6E-04 1.6E-03 5.6E+01

1996 1.1E+02 2.7E+01

1997 5.0E+03 1.8E+02

1998 1.1E+03 6.4E+02

1999 6.7E+02 4.9E-01

2000 8.5E+02 1.8E+02

2001 1.9E+03 2.1E+02

2002 1.9E+03e 2.4E+02e

2003 1.9E+03e 2.4E+02e

a. Calculated from estimated air concentrations in Table C-24, assuming an 

inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks 

indicate no data are available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. It is favorable to the claimant to assume all is 90Sr.

d. It is favorable to the claimant to assume all is 68Ge, Type M.

e. Estimated from average of corresponding values for 1997 to 2001.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 42 of 96

Table 4-22. Estimated annual average intakes of 241Am, 3H, 

239Pu, and 234U for TA-54 (Bq/yr).a

Year Am-241 H-3b Pu-239 U-234

1971–1975

1976 8.6E-03c 4.4E+04 2.8E-03 1.5E-02

1977 4.6E-04 2.5E+04 3.2E-03 2.3E-02

1978 2.0E-04 7.6E+03 7.4E-03 1.4E-02

1979 4.4E-04 4.7E+03 2.0E-03 1.1E-02

1980 3.7E-04 7.1E+03 1.3E-03 1.2E-02

1981 1.4E-04 2.9E+03 9.7E-04 1.2E-02

1982 8.0E-05 3.1E+03 1.3E-03 1.2E-02

1983 8.6E-03c 2.4E+03 6.2E-05 4.1E-03

1984 8.6E-03c 8.4E+03 1.6E-03 9.2E-03

1985 8.6E-03c 1.0E+04 2.1E-03 8.8E-03

1986 1.6E-03 3.7E+03 2.0E-03 8.5E-03

1987 8.4E-04 4.3E+03 1.2E-03 7.4E-03

1988 3.4E-04 3.1E+03 1.6E-03 2.2E-02

1989 7.9E-04 3.8E+03 1.5E-03 1.3E-02

1990 2.8E-04 2.2E+03 4.3E-04 7.2E-03

1991 3.6E-04 1.1E+04 1.6E-03 8.4E-03

1992 1.7E-04 5.9E+03 4.4E-04 2.9E-03

1993 3.4E-04 5.2E+03 7.1E-04 3.1E-03

1994 5.6E-04 4.4E+03 6.3E-04 8.8E-03

1995 1.2E-03 5.8E+03 1.6E-03 5.2E-03

1996 5.6E-03 6.8E+03 7.5E-03 4.9E-03

1997 8.6E-03 1.1E+04 1.3E-02 5.5E-03

1998 1.4E-03 1.7E+04 2.0E-03 6.8E-03

1999 1.4E-03 1.3E+04 2.1E-03 1.1E-02

2000 1.1E-03 1.6E+04 9.0E-04 7.5E-03

2001 9.0E-04 3.1E+04 5.2E-04 5.2E-03

2002 4.6E-03 1.6E+04 9.2E-03 5.3E-03

2003 1.9E-03d 1.9E+04d 3.0E-03d 7.1E-03d

a. Calculated from estimated air concentrations in Table C-25, assuming an 

inhalation rate of 2,400 m3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks 

indicate no data are available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. Assumed to be the highest value of all years for which data are available.

d. Estimated from average of corresponding values for 1998 to 2002.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 43 of 96

Table 4-23. Estimated annual average intakes of 241Am, 3H, 239Pu, 232Th, 

and 234U for TA-55 (Bq/yr).

a

Year Am-241 H-3b Pu-239 Th-232 U-234

1971–1977

1978 7.8E-05

1979 2.1E-05

1980 5.7E-05

1981 1.9E-05

1982 5.5E+03 5.1E-04

1983 1.3E+04 2.1E-04

1984 4.5E+04 2.0E-04

1985 2.1E-04

1986 3.0E+05 4.6E-05

1987 2.5E+04 4.8E-05

1988 9.2E+04 3.0E-03

1989 7.8E+04 4.3E-04

1990 4.9E+04 9.1E-05

1991 2.7E+04 3.9E-04

1992 3.0E+04 2.2E-04

1993 1.9E+04 3.3E-05

1994 6.6E+03 2.3E-05

1995 1.1E-06 4.6E+03 3.2E-06

1996 6.1E-06 9.1E+03 1.7E-05 1.1E-05

1997 7.0E-05 3.5E+03 2.1E-05 8.6E-06

1998 7.4E-07 3.5E+03 1.2E-05 5.9E-06

1999 1.1E-05 5.3E+02 1.2E-05 1.4E-05

2000 6.4E-05 1.9E+03 4.9E-04

2001 1.2E-06 9.7E+02 8.4E-06 2.9E-05 3.3E-05

2002 2.9E-05c 2.1E+03c 1.1E-04c

2003 2.9E-05c 2.1E+03c 1.1E-04c

a. Calculated from estimated air concentrations in Table C-27, assuming an inhalation rate 

of 2,400 m3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no data are 

available for those years.

b. 3

H intake multiplied by 1.5 to account for submersion dose.

c. Estimated from average of corresponding values for 1997 to 2001.

Table 4-24. Estimated annual average intakes of 239 Pu 

and MFPs from the general Los Alamos area (Bq/yr).a

Year Pu-239 MFP

1958 5.5E+02

1959 3.55E-01 2.6E+02

1960 3.55E-01 1.2E+01

1961 3.55E+00 2.9E+02

1962 3.55E-01 4.0E+02

1963 3.55E-01 3.7E+02

1964 3.55E-01 6.1E+01

1965 1.4E+01

1966 1.3E+01

1967 8.88E-02 3.6E+00

1968 1.5E+01

1969 1.2E+01

1970 1.5E+01

a. Calculated from estimated air concentrations in Table C-26, 

assuming an inhalation rate of 2,400 m3

/yr (and multiplying by 

3.7 × 10-2 Bq/pCi); blanks indicate no data are available for 

those years.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 44 of 96

Table 4-25. Estimated air concentrations from resuspension (pCi/m3).

a

Nuclide

Bayo 

Canyon

1978

LA 

Canyon

1977

Mortandad 

Canyon

1977

Acid 

Canyon

1978

Pueblo 

Canyon

1978

Pu-239 3E-05 4E-04 7E-05 2.5E-05

Pu-238 5E-04

Cs-137 1.3E-03 7E03

Sr/Y-90 1E-05

U-238 8E-04

 a. Data are for primary contaminants in each location; other cells are blank.. 

Table 4-26. Area badge data, annual TLD or film results (mrem).a

Year

Site-wide 

maximum TA-3b TA-18b TA-53b TA-54b Backgroundc,d

Geometric 

mean

Geometric 

standard 

deviation

2002 156 115 156 129 236 150 152 1.31

2001e 570 570 224 170 236 150 238 1.69

2000e 268 268 195 212 236 150 208 1.24

1999e 241 143 216 241 233 150 192 1.28

1998 426 157 153 426 213 150 201 1.56

1997e 462 145 197 462 181 150 205 1.60

1996 173 127 241 159 173 150 166 1.27

1995 378 123 378 142 161 150 174 1.56

1994 160 130 127 152 160 150 143 1.11

1993 148 118 128 142 148 150 137 1.11

1992 236 122 123 135 236 144 147 1.31

1991 178 130 136 178 162 150 150 1.14

1990 178 137 136 178 162 164 155 1.13

1989 149 115 149 94 129 152 126 1.22

1988 188 150 188 113 131 155 145 1.21

1987 166 166 153 115 132 152 142 1.16

1986 183 183 181 143 160 152 163 1.11

1985 187 143 187 145 160 150 156 1.12

1984 183 139 183 161 159 150 158 1.11

1983 188 150 188 163 157 150 161 1.10

1982 163 163 153 138 116 146 142 1.14

1981 175 156 175 123 91 139 134 1.29

1980 303 211 303 146 134 152 180 1.40

1979 252 141 252 150 150 153 165 1.27

1978 234 144 182 234 112 137 157 1.33

1977 273 273 164 203 NM 151 183 1.29

1976 261 238 261 172 NM 145 188 1.31

1975 380 380 220 169 NM 158 202 1.47

1974 137 NA 345 169 150 151 191 1.49

1973f 345 128 345 178 NA 184 195 1.54

1972f 160 150 225 NA NA 176 181 1.23

1971 106 138 276 NA NA 169 186 1.43

1970 132 NA NA NA NA NA NA NA

1969 302 NA NA NA NA NA NA NA

1968 302 NA NA NA NA NA NA NA

1967 302 NA NA NA NA NA NA NA

1966 354 NA NA NA NA NA NA NA

1965 423 NA NA NA NA NA NA NA

1967 302 NA NA NA NA 450 [10] NA NA
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 45 of 96

Year

Site-wide 

maximum TA-3b TA-18b TA-53b TA-54b Backgroundc,d

Geometric 

mean

Geometric 

standard 

deviation

1966 354 NA NA NA NA 450 NA NA

1965 423 NA NA NA NA 450 NA NA

a. Dose is based on 8,760 hr/yr and can be adjusted to 2,080 hr/yr by multiplying by 0.237. NA= data not available.

b. Numbers in italics are averages of several area badges in the TA.

c. Backgrounds in italics are a 10- yr average, because actual background is not given.

d. Reported background is the average background for Los Alamos town site plus 2-sigma (or 20%).

e. Neutron dose included for 1997 and 1999 at TA-18 and 2000 and 2001 at TA-3 and TA-18.

f. In these years, TA-36 exposure was elevated due to experiments at adjacent TA-18: 1973 dose, 81 mrem (net); 1972 

dose, 53 mrem (net). For the only other year of data, 1971, dose was not elevated.

 

Table 4-27. Estimated annual deposition of 140La and

 doses from radioactive lanthanum experiments.

a

Year

Doseb

(mrem)

Depositionc

(μCi/m2)

1945 8 4.2E3

1946 8 4.2E3

1947 9 4.7E3

1948 3 1.6E3

1949 12 6.3E3

1950 8 4.2E3

1951 3 1.6E3

1952 1 5.3E2

1953 9 4.7E3

1954 15 7.9E3

1955 23 1.2E4

1956 21 1.1E4

1957 10 5.3E3

1958 6 3.2E3

1959 5 2.6E3

1960 3 1.6E3

a. Applicable to town site (TA-0), TA-2, and vicinity.

b. Source: Kraig (1997, Figure 5).

c. Calculated from Kraig (1997, Equations 2 and 3).
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 46 of 96

Table 4-28. Estimated average external doses from 41Ar released 

from TA-2 (mrem/yr).a

Year Skinb Whole bodyc

1971 2.4E+00 1.6E+00

1972 9.8E-01 6.3E-01

1973 4.2E-01 2.7E-01

1974 4.8E-03 3.1E-03

1975 3.6E-01 2.3E-01

1976 5.2E-01 3.4E-01

1977 4.8E-01 3.1E-01

1978 3.7E-01 2.4E-01

1979 5.4E-01 3.5E-01

1980 7.9E-01 5.1E-01

1981 4.6E-01 3.0E-01

1982 5.3E-01 3.4E-01

1983 6.4E-01 4.1E-01

1984 5.1E-01 3.3E-01

1985 6.0E-01 3.9E-01

1986 4.2E-01 2.7E-01

1987 3.6E-01 2.3E-01

1988 4.1E-01 2.6E-01

1989 3.4E-01 2.2E-01

1990 2.5E-01 1.6E-01

1991 3.1E-01 2.0E-01

1992 2.2E-01 1.4E-01

a. Assumes receptor is at 500 m from the source 2,000 hr/yr, no plume depletion, 

no plume rise (stack height is zero).

b. Calculated using skin dose factor for 41Ar from Eckerman and Ryman (1993). 

c. Calculated using whole-body dose factor for 41Ar from Eckerman and Ryman 

(1993).
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 47 of 96

Table 4-29. Estimated average external doses from G/MAPs 

released from TA-53 (mrem/yr).a

Year Skinb Whole bodyc

1943–1976 Not in operation

1976 9.3E+00 5.8E+00

1977 7.5E+01 4.7E+01

1978 1.9E+02 1.2E+02

1979 1.9E+02 1.2E+02

1980 2.3E+02 1.4E+02

1981 5.6E+02 3.5E+02

1982 4.0E+02 2.5E+02

1983 7.3E+02 4.6E+02

1984 1.2E+03 7.3E+02

1985 2.0E+02 1.2E+02

1986 1.8E+02 1.1E+02

1987 2.4E+02 1.5E+02

1988 1.9E+02 1.2E+02

1989 2.5E+02 1.5E+02

1990 1.9E+02 1.2E+02

1991 9.0E+01 5.7E+01

1992 1.1E+02 7.1E+01

1993 5.1E+01 3.2E+01

1994 7.9E+01 4.9E+01

1995 6.9E+01 4.3E+01

1996 1.7E+01 1.1E+01

1997 3.2E+01 2.0E+01

1998 1.2E+01 7.7E+00

1999 4.7E-01 3.0E-01

2000 1.1E+00 6.8E-01

2001 9.3E+00 5.8E+00

2002 1.1E+01d 6.9E+00d

2003 1.1E+01d 6.9E+00d

a. Assumes receptor is at 500 m from the source 2,000 hr/yr, no plume depletion, 

no plume rise (stack height is zero).

b. Calculated using skin dose factor for 15O from Eckerman and Ryman (1993).

c. Calculated using whole-body dose factor for 41Ar from Eckerman and Ryman 

(1993).

d. Estimated assuming equal to average of corresponding values for 1997 to 2001.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 48 of 96

Table 4-30. Estimated average external doses at TA-21 and TA-72 

from G/MAPs released from TA-53 (mrem/yr).

Year

TA-21 TA-72

Skina Whole bodyb Skina Whole bodyb

1976 6.55E-01 4.10E-01 1.97E+00 1.23E+00

1977 5.30E+00 3.31E+00 1.59E+01 9.93E+00

1978 1.30E+01 8.14E+00 3.91E+01 2.44E+01

1979 1.32E+01 8.28E+00 3.97E+01 2.48E+01

1980 1.62E+01 1.02E+01 4.87E+01 3.05E+01

1981 3.93E+01 2.46E+01 1.18E+02 7.37E+01

1982 2.79E+01 1.75E+01 8.38E+01 5.24E+01

1983 5.13E+01 3.21E+01 1.54E+02 9.62E+01

1984 8.17E+01 5.11E+01 2.45E+02 1.53E+02

1985 1.40E+01 8.76E+00 4.21E+01 2.63E+01

1986 1.25E+01 7.79E+00 3.74E+01 2.34E+01

1987 1.67E+01 1.04E+01 5.01E+01 3.13E+01

1988 1.35E+01 8.42E+00 4.04E+01 2.52E+01

1989 1.74E+01 1.08E+01 5.21E+01 3.25E+01

1990 1.37E+01 8.55E+00 4.11E+01 2.57E+01

1991 6.37E+00 3.98E+00 1.91E+01 1.19E+01

1992 8.01E+00 5.01E+00 2.40E+01 1.50E+01

1993 3.56E+00 2.23E+00 1.07E+01 6.68E+00

1994 5.56E+00 3.48E+00 1.67E+01 1.04E+01

1995 4.85E+00 3.03E+00 1.46E+01 9.10E+00

1996 1.22E+00 7.65E-01 3.67E+00 2.30E+00

1997 2.23E+00 1.39E+00 6.68E+00 4.17E+00

1998 8.68E-01 5.42E-01 2.60E+00 1.63E+00

1999 3.34E-02 2.09E-02 1.00E-01 6.26E-02

2000 7.68E-02 4.80E-02 2.30E-01 1.44E-01

2001 6.57E-01 4.10E-01 1.97E+00 1.23E+00

2002 7.72E-01c 4.83E-01c 2.32E+00c 1.45E+00c

2003 7.72E-01c 4.83E-01c 4.83E-01c 1.45E+00c

a. Calculated using skin dose factor for 15O from Eckerman and Ryman (1993).

b. Calculated using whole-body dose factor for 41Ar from Eckerman and Ryman 

(1993).

c. Estimated assuming equal to average of corresponding values for 1997 to 2001.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/2

6/2010 Page 49 of 56

Table 4-31. Estimated annual site-wide maximum intakes and ambient dose rates for all radionuclides.

Year

Maximum intakes (Bq/yr)a Maximum ambient 

Am-241 H-3 Pu-239 Th-232 U-234 MFP dose rates (mrem/yr) b P/VAPc

1971 9.2E+05 2.5E-02 1.7E+01 276

1972 7.3E+05 2.2E-02 2.1E+01 225

1973 3.6E+05 1.2E-02 4.1E-02 345

1974 4.1E+05 2.9E-01 3.9E-02 137

1975 7.0E+05 8.2E-02 3.8E-02 380

1976 4.9E+05 7.7E-03 7.1E-02 2.4E-01 238

1977 4.6E-04 2.3E+05 1.4E-02 6.6E-02 4.3E-01 273

1978 2.0E-04 2.0E+05 1.1E-02 3.6E-02 2.3E-01 234

1979 4.4E-04 8.8E+05 2.1E-01 5.1E-02 2.1E-01 252

1980 3.7E-04 1.2E+05 1.4E-01 3.0E-02 3.4E-01 303

1981 4.0E-03 9.2E+05 7.7E-03 4.6E-02 2.7E-01 175

1982 8.0E-05 9.2E+05 1.5E-02 6.3E-02 2.1E-01 3.6E+04 163

1983 1.9E-05 6.7E+05 1.7E-02 3.5E-02 1.6E-01 5.2E+05 188

1984 1.4E+06 2.2E-02 4.2E-02 3.1E-01 4.9E+05 183

1985 6.2E+05 3.8E-02 6.7E-02 2.4E-01 3.9E+01 187

1986 1.6E-03 3.9E+05 3.8E-02 1.2E-01 4.9E-01 2.0E+01 183

1987 8.4E-04 2.5E+05 1.3E-02 1.7E-01 2.4E-01 3.9E+01 166

1988 5.9E-04 2.4E+06 1.0E-02 9.8E-02 2.2E-01 2.0E+01 188

1989 7.9E-04 3.4E+06 7.6E-03 7.1E-02 8.5E+01 2.0E+01 149

1990 2.8E-04 1.3E+06 4.2E-03 3.8E-02 2.0E-01 1.6E+01 178

1991 3.6E-04 1.1E+06 1.6E-03 8.4E-03 2.1E-01 3.9E+01 178

1992 4.0E-04 8.6E+04 1.3E-03 4.5E-01 5.4E-01 1.4E+02 236

1993 1.7E-03 1.4E+05 4.9E-03 9.7E-01 2.6E-01 2.0E+03 148

1994 5.7E-04 5.0E+04 1.0E-03 8.8E-03 7.6E-02 6.1E+01 160

1995 1.3E-03 2.4E+04 1.6E-03 8.0E-03 5.2E+00 4.4E+02 161

1996 5.6E-03 3.2E+04 7.5E-03 3.2E-05 2.2E-02 2.7E+01 241

1997 8.6E-03 1.2E+04 1.3E-02 7.4E-05 5.5E-03 1.8E+02 462

1998 1.4E-03 3.3E+04 2.3E-03 8.2E-05 6.8E-03 6.4E+02 426

1999 1.4E-03 1.3E+04 2.1E-03 4.3E-05 1.1E-02 7.6E-01 241

2000 1.3E-03 1.6E+04 9.0E-04 2.5E-05 7.5E-03 1.8E+02 268

2001 9.0E-04 1.6E+05 5.2E-04 2.9E-05 1.4E-02 2.1E+02 570

2002 4.6E-03 3.7E+04 9.2E-03 5.0E-05 5.3E-03 2.4E+02 156

2003 1.9E-03 3.7E+04 3.0E-03 5.0E-05 7.1E-03 2.4E+02

a. Values are the maximum annual average intake reported for all technical areas in Tables 4-1 through 4-23 for each radionuclide, and are based on an inhalation rate 

of 2,400 m3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no release or air concentration data were available.

b. It should be assumed that the intake is composed solely of 137Cs, except for the organs bone surface and red bone marrow, in which case 90Sr should be assumed 

(Brackett 2010).

c. The dose reconstructor should assume all is either 68Ge, Type M, or 75Se, Type F, depending on which is higher for the organ of interest (Brackett 2010).
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 50 of 96

4.5 ATTRIBUTIONS AND ANNOTATIONS

Where appropriate in the preceding text, bracketed callouts have been inserted to indicate 

information, conclusions, and recommendations to assist in the process of worker dose 

reconstruction. These callouts are listed in this section with information that identifies the source and 

justification for each item. Conventional references are provided in the next section that link data, 

quotations, and other information to documents available for review on the Oak Ridge Associated 

Universities (ORAU) Team servers.

[1] Buddenbaum, Jack E. ENSR. Health Physicist. August 2004.

Emissions and monitoring data was provided by Scott Miller and Joe Graf of LANL.

[2] McDowell-Boyer, Laura M. ORAU Team. Environmental Engineer. August 2006.

The procedural document for development of TBDs (ORAUT-PROC-0031, ORAUT 2007) 

directs that the occupational environmental dose analysis be limited “to the 10 radionuclides 

that contribute to at least 95% of the dose.” The determination of which radionuclides these 

are is the subject of Section 4.2.1.2 in this document. Due to the changing missions and 

operations at LANL over the years, the 10 radionuclides that fulfill this requirement have varied 

over the years. Therefore, a decision was made to select the radionuclides for each year that 

contributed the highest doses that summed to at least 95% of the total estimated dose for that 

year. 

[3] McDowell-Boyer, Laura M. ORAU Team. Environmental Engineer. August 2006.

In the absence of site-specific information, the AMAD of 5 μm is consistent with ICRP default 

recommendations (ICRP 1995) for worker exposure to airborne particulates

[4] McDowell-Boyer, Laura M. ORAU Team. Environmental Engineer. August 2006.

When emissions estimates did not specify isotopic contributions, the isotope with the highest 

effective dose factor was selected as representative of the group. For example, for plutonium 

emissions, all of the effluent was assumed to be 239Pu, which has the highest effective dose 

factor of all radionuclides in the group (238Pu, 239Pu, 240Pu, 241Pu, 241Am). This assumption 

tended to maximize the estimated potential impact of plutonium so that the importance of this 

group was not underestimated in the screening analysis.

[5] McDowell-Boyer, Laura M. ORAU Team. Environmental Engineer. August 2006.

Air monitoring was the preferred source of data for estimation of air concentrations of air 

particulates at LANL. These data, which are available for many TAs over time, represent 

contributions from stack or vent effluents and area sources (such as contaminated soil) within 

the TA in which they are located, but they also represent contributions from nearby TAs. 

[6] McDowell-Boyer, Laura M. ORAU Team. Environmental Engineer. August 2006.

The ratioing method is, in effect, an empirically-derived χ/Q, that represents the relationship 

between the air concentration and the source term. Unlike model-derived χ/Q values, 

however, this empirical value includes the contributions of resuspended contaminated soil, and 

thus it is likely to be a higher value than might be predicted by a simplified dispersion model. It 

is specific for the conditions under which it was measured, the location of the air monitors 

relative to the source(s), and the source configurations themselves. While it cannot be

manipulated to represent other source configurations, atmospheric conditions, or downwind 

distances, it is a reasonable estimate in the absence of more complex dispersion models that

address resuspension.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 51 of 96

[7] McDowell-Boyer, Laura M. ORAU Team. Environmental Engineer. August 2006.

The linear regression analysis was carried out using a spreadsheet to evaluate whether the 

reported emissions for TA-3 and TA-21 correlated with the measured air concentrations at 

each TA, and how strong this correlation was. The results indicated that the air concentrations 

were linearly correlated, and that the relationship could be characterized as moderate to 

strong according to the calculated correlation coefficients. The fact that the average ratios 

were almost identical gave further confidence that this observed relationship is causal rather 

than coincidental. 

[8] McDowell-Boyer, Laura M. ORAU Team. Environmental Engineer. August 2006.

Although the ratioing method does not directly allow evaluation of the effect of different source 

configurations on nearby air concentrations, the following information is pertinent. The stacks 

from which most of the plutonium is released at TA-3 are approximately 16 m in height. The 

comparable stack at TA-21 is 10 m in height. This difference in stack heights did not 

significantly affect the calculated ratio. This could be because wake effects alter plume 

dispersion similarly in both areas, or possibly because resuspension dominates the measured 

air concentration in both areas (if plutonium concentrations in soil are similar in both locations). 

It is further pertinent to consider that for plutonium in particular, releases from TA-3 and TA-21 

were significantly greater that from other areas (more than 2 orders of magnitude). Thus, 

although there could be some error in not accounting for differential source configurations, the 

TA-3 and TA-21 measurements are used directly to define the site-wide maximum intakes, 

and the ratioing method thus does not affect these intake estimates.

[9] McDowell-Boyer, Laura M. ORAU Team. Environmental Engineer. August 2006.

The isotopic ratio, in atom percent, of natural uranium is 0.0055%:0.72%:99.28% for 

234U:235U:238U, and that for depleted uranium is 0.0007%:0.20%:99.80% (DOE 2001). The 

specific activity of natural uranium is 6.75 × 10-7 Ci/g, and of depleted uranium is 

4.76 × 10-

7 Ci/g, both of which are smaller than that for enriched uranium. Therefore, the 

assumption that all uranium is enriched uranium provides an upper bound on the calculated 

total activity of uranium based on reported total uranium values. 

[10] Buddenbaum, Jack E. ENSR. Health Physicist. August 2004.

Emissions and monitoring data was provided by Scott Miller and Joe Graf of LANL.
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 52 of 96

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National Laboratory, 1944–1962,” Health Physics, volume 73, number 4.

LANL (Los Alamos National Laboratory), undated, ‘Summary of Significant Atmospheric Releases, 

Through 12/31/1972,’ unpublished .pdf file, LAHDRA 2103. [SRDB Ref ID: 41597]

LANL (Los Alamos National Laboratory), 1994, Environmental Surveillance at Los Alamos during 

1992, LA-12764-ENV, Los Alamos National Laboratory, Los Alamos, New Mexico. [SRDB Ref 

ID: 35740]

LANL (Los Alamos National Laboratory), 1999, Environmental Surveillance at Los Alamos during 

1998, LA-13633-ENV, Los Alamos National Laboratory, Los Alamos, New Mexico. [SRDB Ref 

ID: 35741]

LANL (Los Alamos National Laboratory), 2000, Environmental Surveillance at Los Alamos during 

2000, LA-13861-ENV, Los Alamos National Laboratory, Los Alamos, New Mexico. [SRDB Ref 

ID: 13690 and 13692]

LANL (Los Alamos National Laboratory), 2002, Environmental Surveillance at Los Alamos during 

2002, LA-14085-ENV, Los Alamos National Laboratory, Los Alamos, New Mexico. [SRDB Ref 

ID: 13551]

LANL (Los Alamos National Laboratory), 2003, update of LANL AIRNET Web site, Meteorology and

Air Quality Group, Los Alamos, New Mexico. [SRDB Ref ID: 12415]

http://www.lanl.gov/orgs/rres/maq/AirConc_AllData.htm#LOS (changed to 

www.airquality.lanl.gov/airnet/air_data.shtml), accessed October 8, 2003.

LASL (Los Alamos Scientific Laboratory), 1959, Los Alamos Environmental Monitoring Program, 1959 

Summary Report, Los Alamos, New Mexico. Unpublished. [SRDB Ref ID: 13571]

LASL (Los Alamos Scientific Laboratory), 1960, Los Alamos Environmental Monitoring Program, 1960 

Summary, Los Alamos, New Mexico. Unpublished. [SRDB Ref ID: 13565]

LASL (Los Alamos Scientific Laboratory), 1972, Environmental Surveillance at Los Alamos During 

1972, Environmental Studies Group, Los Alamos, New Mexico. [SRDB Ref ID: 28601]

LASL (Los Alamos Scientific Laboratory), 1973, Environmental Surveillance at Los Alamos During 

1973, Environmental Studies Group, LA-5586, Los Alamos, New Mexico. [SRDB Ref ID: 

13575]
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 54 of 96

LASL (Los Alamos Scientific Laboratory), 1979, Formerly Utilized MED/AEC Sites Remedial Action 

Program; Radiological Survey of the Bayo Canyon, DOE/EV-0005/15, Los Alamos, New 

Mexico. [SRDB Ref ID: 13687]

NCRP (National Council on Radiation Protection and Measurements), 1996, Screening Models for 

Releases of Radionuclides to Atmosphere, Surface Water, and Ground, Report 123, 

Bethesda, Maryland.

NIOSH (National Institute for Occupational Safety and Health), 2006, SEC Petition Evaluation Report 

Petition SEC-00061, Office of Compensation Analysis and Support, Cincinnati, Ohio, 

August 8.

NIOSH (National Institute for Occupational Safety and Health), 2007a, Radiation Exposures Covered 

for Dose Reconstructions Under Part B of the Energy Employees Occupational Illness 

Compensation Program Act, OCAS-IG-003, Rev. 0, Office of Compensation Analysis and 

Support, Cincinnati, Ohio, November.

NIOSH (National Institute for Occupational Safety and Health), 2007b, SEC Petition Evaluation Report 

Petition SEC-00051, Office of Compensation Analysis and Support, Cincinnati, Ohio, February 

1, 2007.

ORAUT (Oak Ridge Associated Universities Team), 2004, Technical Basis Document for the Los 

Alamos National Laboratory – Site Description, ORAUT-TKBS-0010-2, Rev. 00, Oak Ridge, 

Tennessee, May 7.

ORAUT (Oak Ridge Associated Universities Team), 2007, Site Profile and Technical Basis Document

Development, ORAUT-PROC-0031, Rev. 02, Oak Ridge, Tennessee, August 17.

Purtymun, W. D., A. K. Stoker, and R. Peters, 1980, Radioactivity in Soils and Sediments in and 

Adjacent to the Los Alamos Area, 1974-1977, LA-8234-MS, Los Alamos Scientific Laboratory, 

Los Alamos, New Mexico. [SRDB Ref ID: 13586]
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 55 of 96

Tables A-1 through A-22 contain emissions data that have been reported by year and radionuclide for 

many of the TAs at LANL. In recent years, effluents have been reported by stack and/or building vent; 

in these cases, the effluents were summed within a TA. For years up to and including 1970, the 

reported effluent releases rely on data from the Centers for Disease Control and Prevention LAHDRA 

project; in the year 1970 and after, the reported releases are from annual environmental surveillance 

reports. Blank values in these tables indicate no data. 

Table A-1. Estimated source emissions from TA-1 (μCi/yr).

Year Pu

1943 No source estimates for this year

1944 No source estimates for this year

1945 2.11E+05

1946 2.65E+05

1947 4.21E+05

1948–2001 No source estimates for these years

2002

2003

Table A-2. Estimated source emissions from TA-2 (μCi/yr).

Year Ar-41

1943–1966 No source estimates for this year

1967 1.55E+10

1968 6.48E+09

1969 1.80E+09

1970 1.30E+09

1971 1.57E+09

1972 6.40E+08

1973 2.73E+08

1974 3.12E+06

1975 2.37E+08

1976 3.39E+08

1977 3.15E+08

1978 2.39E+08

1979 3.51E+08

1980 5.13E+08

1981 3.01E+08

1982 3.42E+08

1983 4.18E+08

1984 3.35E+08

1985 3.90E+08

1986 2.76E+08

1987 2.32E+08

1988 2.64E+08

1989 2.22E+08

1990 1.60E+08

1991 2.03E+08

1992 1.40E+08

1993–2003 Not in operation

ATTACHMENT A

SOURCE EMISSIONS

Page 1 of 16
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Table A-3. Estimated source emissions from TA-3 (μCi/yr).

Year Am-241 H-3 I-131 Pu Th-232 U MFP P/VAP

1943–1951 No source estimates for these years

1952 1.00E+01

1953 2.30E+02

1954 1.30E+03

1955 1.89E+03

1956 1.49E+03

1957 1.12E+03

1958 3.21E+03

1959 8.90E+02

1960 2.97E+03

1961 1.92E+03

1962 1.80E+03

1963 6.52E+05 8.60E+02

1964 2.97E+05 6.50E+02

1965 3.81E+05 1.59E+03

1966 1.88E+03

1967 4.19E+03

1968 6.05E+03

1969 1.16E+04

1970 1.35E+04

1971 8.90E+07 6.95E+03 1.43E+04 5.80E+02

1972 4.80E+07a 7.40E+03a 7.90E+03a 3.60E+02a

1973 4.23E+03 7.30E+03 1.56E+01 5.93E+02 1.28E+04

1974 4.73E+03 1.47E+03 2.02E+02 3.42E+02

1975 2.20E+07 1.36E+03 4.20E+02 1.94E+02 1.84E+02

1976 0.00E+00 3.00E+02 3.95E+01 3.63E+02 4.15E+02

1977 4.00E+08 8.80E+01 3.35E+01 3.38E+02 4.81E+02

1978 9.98E+07 8.10E+01 5.83E+01 1.85E+02 4.03E+02

1979 3.02E+09 1.58E+02 1.07E+03 2.61E+02 4.72E+02

1980 4.55E+06 9.40E+01 7.41E+02 1.55E+02 4.24E+02

1981 8.99E+08 4.40E+01 3.96E+01 2.36E+02 1.72E+02

1982 1.94E+09 7.85E+02 7.44E+01 3.21E+02 7.63E+01

1983 2.28E+09 8.30E+01 8.85E+01 1.81E+02 1.71E+01

1984 1.78E+09 7.30E+01 1.15E+02 2.14E+02 4.15E+01

1985 2.12E+09 1.46E+02 1.95E+02 3.44E+02 3.47E+01

1986 1.23E+09 3.80E+01 1.94E+02 6.31E+02 4.79E+01

1987 8.51E+08 6.49E+01 8.68E+02 2.16E+01

1988 8.35E+09 5.19E+01 5.00E+02 2.97E+01

1989 2.91E+08 3.91E+01 3.65E+02 3.82E+01

1990 4.96E+08 2.16E+01 1.96E+02 3.89E+01

1991 2.05E+08 3.08E+01 2.44E+02 1.41E+01

1992 1.15E+08 2.73E+00 1.98E+02 8.42E+00

1993 7.63E+07 1.74E+00 2.18E+02 6.05E+00

1994 5.38E+07 6.00E+00 1.96E+02 3.84E+01

1995 4.02E+00 2.25E+06 5.35E+01 1.53E+02 9.38E+02 9.38E+02

1996 1.22E+00 2.31E+01 1.64E-01 3.87E+01

1997 3.70E-01 3.50E+00 3.80E-01 2.20E+01

1998 1.60E+00 1.10E+01 4.20E-01 3.10E+01 6.70E+00

1999 2.60E+00 2.10E+01 2.20E-01 7.60E+00

2000 1.80E-01 3.20E+00 1.30E-01 6.80E+00

2001 2.60E-01 9.20E+00 1.40E-01 7.10E+00

ATTACHMENT A

SOURCE EMISSIONS

Page 2 of 16
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 57 of 96

Year Am-241 H-3 I-131 Pu Th-232 U MFP P/VAP

2002

2003

a. Value taken from LASL (1972) due to inconsistencies or omissions in database for 1972.

Table A-4. Estimated source emissions from TA-9 (μCi/yr).

Year H-3

1943–1971 No source estimates for these years

1972 7.00E+08a

1973 3.60E+07b

1974 1.30E+06

1975 No source estimates for this year

1976 1.29E+08

1977 2.60E+07

1978 2.60E+06

1979 5.00E+06

1980 5.00E+06

1981–2001 No source estimates for these years

2002

2003

a. Value taken from LASL (1972) due to inconsistencies or omissions in 

database for 1972.

b. Value taken from LASL (1973) due to inconsistencies in database for 

1973.

Table A-5. Estimated source emissions from TA-10 (μCi/yr).

Year U

1943 No source estimates for this year

1944 1.0

0E+04

1945 1.00E+04

1946 3.00E+04

1947 4.00E+04

1948 6.00E+04

1949 1.00E+05

1950 5.00E+05

1951 2.00E+05

1952 2.00E+05

1953 2.00E+05

1954 4.00E+03

1955 3.30E+04

1956 3.50E+04

1957 1.10E+04

1958 7.00E+03

1959 1.20E+04

1960 7.00E+03

1961 8.82E+05

1962 1.82E+05

1963 5.00E+04

1964–2001 No source estimates for these years

2002

2003

ATTACHMENT A

SOURCE EMISSIONS

Page 3 of 16
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Table A-6. Estimated source emissions from TA-15 (μCi/yr).

Year H-3 Th-232 U

1943 No source estimates for this year

1944 6.00E+04

1945 1.20E+05

1946 2.40E+05

1947 3.60E+05

1948 5.40E+05

1949 8.70E+05

1950 4.50E+06

1951 2.00E+06

1952 1.80E+06

1953 1.60E+06

1954 1.49E+06

1955 1.19E+06

1956 7.93E+05

1957 1.20E+06

1958 1.07E+06

1959 5.16E+05

1960 7.14E+05

1961 3.48E+05

1962 4.73E+05

1963 3.96E+05

1964 5.97E+05

1965 5.72E+05

1966 9.42E+05

1967 3.59E+09 2.00E+09 7.20E+05

1968 4.50E+09 2.00E+09 5.37E+05

1969 4.50E+09 4.28E+05

1970 2.87E+10 3.07E+05

1971 2.66E+09 4.95E+05

1972 1.81E+09 1.64E+05

1973 9.30E+08a

1974–1977 No source estimates for these years

1978 7.16E+07

1979–1991 No source estimates for these years

1992 2.29E+03

1993 4.94E+03

1994 7.87E+03

1995–2001 No source estimates for these years

2002

2003

a. Value taken from LASL (1973) due to omission in database for 1973.

ATTACHMENT A

SOURCE EMISSIONS

Page 4 of 16
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Table A-7. Estimated source emissions from TA-16 (μCi/yr).

Year H-3 U

1943–53 No source estimates for these years

1954 3.80E+04

1955 No source estimates for this year

1956 No source estimates for this year

1957 1.40E+04

1958 No source estimates for this year

1959 1.00E+03

1960 5.00E+04

1961 No source estimates for this year

1962 No source estimates for this year

1963 4.80E+04

1964 3.00E+03

1965 4.00E+03

1966 No source estimates for this year

1967 5.00E+03

1968 3.90E+04

1969 3.00E+03

1970 1.10E+04

1971 2.00E+03

1972–1991 No source estimates for these years

1992 6.28E+04

1993 7.73E+05

1994 2.46E+07

1995 8.90E+07

1996 9.90E+07

1997 9.80E+07

1998 2.40E+08

1999 1.60E+08

2000 2.60E+08

2001 7.90E+09

2002

2003

Table A-8. Estimated source emissions from TA-18 (μCi/yr).

Year U

1943–1978 No source estimates for these years

1979 3.95E+00

1980–2001 No source estimates for these years

2002

2003

ATTACHMENT A

SOURCE EMISSIONS

Page 5 of 16
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Table A-9. Estimated source emissions from TA-21 (μCi/yr).

Year Am-241 H-3 Pu U MFP

1943–1947 No source estimates for these years (see TA-1 data)

1948 1.55E+05

1949 1.55E+05

1950 1.85E+05

1951 2.70E+04

1952 5.70E+04

1953 3.50E+04

1954 2.20E+04

1955 8.80E+04

1956 7.60E+04

1957 7.40E+04

1958 8.00E+04

1959 1.86E+05

1960 3.53E+04

1961 6.24E+03

1962 7.99E+03 6.29E+03

1963 2.87E+04 3.05E+04

1964 1.24E+04 2.31E+03

1965 9.31E+03 9.13E+03

1966 1.04E+04 1.00E+04

1967 9.99E+03 6.91E+03

1968 1.94E+03 1.30E+03

1969 4.17E+03 3.56E+03

1970 2.82E+03 1.03E+03

1971 5.00E+06 1.79E+03 1.18E+03

1972 2.17E+03 1.20E+03a

1973 4.00E+06b 1.40E+03 9.08E+02 1.00E+00

1974 5.71E+00 6.00E+02 2.90E+00

1975 3.06E+08 1.11E+01 7.21E+02 1.44E+00

1976 9.50E+07 1.22E+01 8.70E+02 5.50E-01

1977 1.33E+08 9.99E+00 3.17E+02 3.26E+00

1978 3.40E-02 3.07E+01 3.05E+02 1.03E+00

1979 1.90E-02 9.49E+07 6.46E+00 6.55E+02 4.68E-01

1980 6.10E-02 1.06E+08 2.27E+00 6.33E+02 4.18E+00

1981 2.90E-02 1.08E+08 1.31E+01 1.02E+03 2.80E+00

1982 3.50E-02 1.69E+08 1.58E+01 1.04E+03 4.35E-01

1983 9.50E-02 1.80E+08 9.92E+00 7.06E+02 7.94E-01

1984 8.02E+08 1.73E+01 9.90E+02 3.14E-01

1985 3.67E+08 1.06E+01 3.82E+02 3.61E-01

1986 4.48E+08 3.57E+00 2.12E+02 3.24E-01

1987 5.96E+08 1.43E+00 2.07E+02 1.88E-01

1988 5.28E+08 7.13E-01 5.88E+01 1.54E-01

1989 4.55E+08 1.39E+00 2.89E+01 3.10E-02

1990 4.39E+08 9.01E-01 4.32E+01 1.30E-02

1991 3.24E+08 8.45E-01 9.20E+01 3.00E-02

1992 4.29E+08 8.70E-01 5.20E+01 2.40E-02

1993 4.26E+08 8.10E-01 5.17E+01 1.00E-02

1994 3.32E+08 2.40E+00 1.82E+02 5.00E-02

1995 7.72E-03 7.12E+08 6.41E-01 1.71E+00

ATTACHMENT A

SOURCE EMISSIONS

Page 6 of 16
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Year Am-241 H-3 Pu U MFP

1996 3.90E+08

1997 2.10E+08

1998 4.60E+08

1999 4.90E+08

2000 9.40E+08

2001 4.90E+08

2002

2003

a. Value taken from LASL (1972) due to inconsistencies or omissions in database for 1972.

b. Value taken from LASL (1973) due to inconsistencies in database for 1973.

Table A-10. Estimated source emissions from TA-33 (μCi/yr).

Year H-3 U

1943–1965 No source estimates for these years

1966 1.00E+04

1967–1970 No source estimates for these years

1971 4.10E+09

1972 2.90E+09a

1973 3.90E+09b

1974 5.92E+09

1975 3.48E+09

1976 1.35E+09

1977 3.70E+10

1978 1.78E+10

1979 1.05E+10

1980 6.97E+09

1981 6.09E+09

1982 1.36E+10

1983 4.41E+09

1984 7.11E+09

1985 4.87E+09

1986 6.66E+09

1987 1.00E+09

1988 No source estimates for this year

1989 1.77E+09

1990 8.54E+08

1991 2.54E+08

1992 3.18E+08

1993 3.50E+08

1994 4.56E+08

1995 1.09E+08

1996 No source estimates for this year

1997 4.30E+07

1998 6.50E+07

1999 9.40E+08

2000 1.20E+09

ATTACHMENT A

SOURCE EMISSIONS

Page 7 of 16
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 62 of 96

Year H-3 U

2001 4.60E+08

2002

2003

a. Value taken from LASL (1972) due to inconsistencies or omissions in 

database for 1972.

b. Value taken from LASL (1973) due to inconsistencies in database for 

1973.

Table A-11. Estimated source emissions from TA-35 (μCi/yr).

Year Am-241 H-3 Pu U MFP P/VAP

1943–1966 No source estimates for these years

1967 6.60E+00

1968 5.90E+00

1969 5.57E+00

1970 4.21E+00

1971 3.13E+09 7.37E+00

1972 2.50E+09a 1.79E+01

1973 1.23E+09 2.35E+00

1974 1.40E+09 8.01E+00

1975 2.39E+09 5.91E+00

1976 1.66E+09 2.37E+00

1977 7.86E+08 8.19E-01

1978 6.76E+08 1.96E+00

1979 1.30E+09 7.40E+00

1980 2.50E+07 2.07E-01

1981 2.66E-01

1982 1.30E+00

1983 6.00E+06 9.26E-01

1984 2.06E+08 4.17E-01

1985 5.28E+06 5.61E-01

1986 4.76E+07 3.63E-01

1987 1.55E+08 6.36E-01

1988 1.18E+08 1.72E-01

1989 1.82E+07 6.80E-01

1990 4.00E+04 8.95E-01

1991 4.30E+00 1.22E+00

1992 1.00E+05 3.58E-01

1993 MDAb 2.70E-01

1994 3.90E-01

1995 3.55E-02 2.97E-01 6.93E-01 1.63E+00 1.63E+00

1996–2001 No source estimates for these years

2002

2003

a. Value taken from LASL (1972) due to inconsistencies or omissions in database for 1972.

b. MDA = minimum detectable activity.

ATTACHMENT A

SOURCE EMISSIONS

Page 8 of 16
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Table A-12. Estimated source emissions from TA-36 (μCi/yr).

Year U

1943–1957 No source estimates for these years

1958 4.30E+04

1959 8.00E+03

1960 1.40E+04

1961 No source estimates for this year

1962 1.00E+04

1963 1.40E+04

1964 4.00E+03

1965 2.00E+04

1966 2.80E+04

1967 4.80E+04

1968 2.70E+04

1969 1.90E+04

1970 6.00E+03

1971 1.00E+04

1972 4.00E+03

1973–2001 No source estimates for these years

2002

2003

Table A-13. Estimated source emissions from TA-39 (μCi/yr).

Year U

1943–53 No source estimates for these years

1954 1.91E+05

1955 1.48E+05

1956 1.73E+05

1957 2.66E+05

1958 2.85E+05

1959 1.89E+05

1960 1.16E+05

1961 1.63E+05

1962 1.63E+05

1963 1.26E+05

1964 1.15E+05

1965 1.07E+05

1966 1.23E+05

1967 2.00E+05

1968 5.00E+04

1969 6.60E+04

1970 5.10E+04

1971 8.70E+04

1972 1.10E+05

1973–2001 No source estimates for these years

2002

2003

ATTACHMENT A

SOURCE EMISSIONS

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Table A-14. Estimated source emissions from TA-41 (μCi/yr).

Year H-3 Pu U

1943–1966 No source estimates for these years

1967 1.20E+02

1968 3.30E+01

1969 9.00E+00

1970 7.80E+00

1971 3.20E+08 1.90E+01

1972 1.10E+08a 1.10E+01

1973 5.90E+07 1.52E+00

1974–1978 No source estimates for these years

1979 1.43E+08

1980 4.14E+08

1981 1.26E+08

1982 1.30E+08

1983 9.74E+08

1984 4.78E+09

1985 1.27E+09

1986 1.32E+09

1987 4.70E+08

1988 1.73E+09

1989 1.16E+10

1990 4.44E+09

1991 3.84E+09

1992 2.92E+08

1993 4.83E+08 1.00E-02

1994 1.72E+08 2.00E-02

1995 7.85E+07 1.56E-02 9.02E-03

1996 1.10E+08

1997 4.20E+07

1998 3.60E+07

1999 1.30E+07

2000 6.30E+06

2001 5.30E+08

2002

2003

a. Value taken from LASL (1972) due to inconsistencies or omissions 

noted in database for 1972.

Table A-15. Estimated source emissions from TA-42 (μCi/yr).

Year Pu source

1943–1968 No source estimates for these years

1969 8.10E+02

1970–2001 No source estimates for this year

2002

2003

ATTACHMENT A

SOURCE EMISSIONS

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Table A-16. Estimated source emissions from TA-43 (μCi/yr).

Year Am-241 Pu U

1943–1972 No source estimates for these years

1973 4.80E-01

1974 6.91E+00

1975 1.65E+00

1976 7.72E+00

1977 4.65E+00

1978 1.55E+00

1979 7.55E-01

1980 1.84E-01

1981 3.68E-01

1982 1.39E+00

1983 3.33E+00

1984 1.05E+00

1985 1.80E+00

1986 2.91E+00

1987 5.06E-01

1988 1.46E+00

1989–1994 No source estimates for these years

1995 2.69E-01 5.27E-01 1.12E+00

1996–2001 No source estimates for these years

2002

2003

Table A-17. Estimated source emissions from TA-46 (μCi/yr).

Year U source

1950–70 Operations started in 1950; no source estimates 

for these years

1971 4.00E+00

1972 1.20E+02a

1973 2.17E+00

1974 4.10E-01

1975 5.20E-01

1976 3.10E-01

1977 4.00E-03

1978 2.53E+01

1979 2.27E+00

1980 1.48E+00

1981 1.38E+01

1982 2.03E+00

1983 3.60E-02

1984 5.10E-02

1985 2.80E-02

1986 4.00E-03

1987–2001 No source estimates for these years

2002

2003

a. Value taken from LASL (1972) due to inconsistencies or omissions in 

database for 1972.

ATTACHMENT A

SOURCE EMISSIONS

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Table A-18. Estimated source emissions from TA-48 (μCi/yr).

Year Am-241 Pu U MFP P/VAP G/MAP

195X–1966 Started operations in mid 1950s; no source estimates for these years

1967 1.10E+02

1968 1.50E+02

1969 1.30E+02

1970 5.70E+01

1971 1.89E+01

1972 1.13E+02 8.00E+00a

1973 1.98E+01 1.96E+00 1.02E+03

1974 2.39E+01 1.26E+00 9.41E+02

1975 1.23E+01 3.44E+00 7.22E+02

1976 5.02E+00 1.12E+02 1.23E+03

1977 8.38E+00 5.52E+01 2.19E+03

1978 1.91E+00 1.12E+01 1.17E+03

1979 3.36E-01 1.08E+01 1.07E+03

1980 1.57E+00 6.66E-01 1.75E+03

1981 1.32E+00 2.31E+00 1.37E+03

1982 9.95E+00 7.33E+00 1.09E+03

1983 3.30E+00 5.11E-01 8.16E+02

1984 2.55E+00 1.34E+00 1.57E+03

1985 2.07E+00 1.91E+00 1.21E+03

1986 2.85E+00 6.11E-01 2.50E+03

1987 6.15E-01 1.58E+00 1.25E+03

1988 7.24E-01 2.20E-01 1.11E+03

1989 1.49E+00 2.70E-01 4.35E+05

1990 1.48E+00 1.70E-01 1.04E+03

1991 5.86E-01 1.08E+03 1.00E+05 1.78E+05

1992 6.72E+00 4.17E-01 2.74E+03 3.79E+04

1993 3.16E+00 1.42E+00 1.35E+03 7.59E+04

1994 3.22E+00 4.00E-01 3.90E+02 8.13E+04

1995 1.71E+00 3.10E+00 5.37E-01 2.64E+04 2.64E+04

1996 5.00E-03 1.10E-02 1.00E+02

1997 3.60E-04 2.50E-03 1.40E-01 1.80E+03

1998 3.70E-04 1.10E+02

1999 6.10E-04 3.90E+03

2000 1.70E+04

2001 2.30E+03

2002

2003

a. Value taken from LASL (1972) due to inconsistencies or omissions in database for 1972.

ATTACHMENT A

SOURCE EMISSIONS

Page 12 of 16
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Table A-19. Estimated source emissions from TA-50 (μCi/yr).

Year Am-241 Pu Th-232 U MFP

1943–1966 No source estimates for these years

1967 1.01E+02

1968 6.88E+01

1969 4.20E+01

1970 2.04E+01

1971 1.60E+01

1972 2.74E+01

1973 2.49E+00 1.72E+01

1974 3.90E+00 8.83E+01

1975 4.11E+00 4.22E+01

1976 1.10E+00 2.75E+01

1977 6.96E+01 8.58E+01

1978 1.74E+01 3.99E+01

1979 2.90E+00 1.06E+01

1980 1.17E+00 8.25E+00

1981 1.79E+00 2.42E+01

1982 6.54E+00 1.45E+01

1983 5.55E+00 9.08E+00

1984 3.67E+00 8.90E+00

1985 2.02E+00 8.49E+00

1986 2.88E+00 2.01E+01

1987 4.51E+00 2.16E+01

1988 2.05E+00 1.38E+01

1989 4.59E-01 9.78E+00

1990 1.48E-01 3.92E+00

1991 1.38E+00 3.09E+00

1992 5.50E-01 3.57E+00

1993 2.80E-01 3.75E+00

1994 3.10E-01 6.79E+00

1995 6.26E-02 7.21E-01

1996 1.10E-02 4.20E-02 1.90E-01

1997 8.40E-03 5.41E-02 1.30E-03

1998 6.50E-03 1.50E-02 7.70E-02 1.90E-01

1999 1.30E-01 5.11E-02 3.70E-02 1.90E-02

2000 9.80E-03 5.30E-02

2001 5.80E-05 4.30E-02

2002

2003

ATTACHMENT A

SOURCE EMISSIONS

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Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 68 of 96

Table A-20. Estimated source emissions from TA-53 (μCi/yr).

Year H-3 I-131 P/VAP G/MAP

1943–1973 No source estimates for these years

1974 1.00E-02

1975 1.00E-02

1976 1.71E+08 5.89E+09

1977 2.90E+08 4.76E+10

1978 1.17E+11

1979 1.19E+11

1980 1.46E+11

1981 6.59E+06 3.53E+11

1982 2.72E+05 1.8E+08 2.51E+11

1983 2.6E+09 4.61E+11

1984 2.70E+07 2.5E+09 7.34E+11

1985 6.96E+06 2.0E+05 1.26E+11

1986 6.10E+06 1.0E+05 1.12E+11

1987 1.52E+07 2.0E+05 1.50E+11

1988 4.27E+06 1.0E+05 1.21E+11

1989 8.20E+06 1.0E+05 1.56E+11

1990 2.84E+06 8.0E+04 1.23E+11

1991 8.87E+05 2.0E+05 5.72E+10

1992 4.21E+07 7.3E+05 7.20E+10

1993 4.86E+07 1.0E+07 3.20E+10

1994 1.46E+07 3.1E+05 5.00E+10

1995 3.17E+06 2.9E+05 4.36E+10

1996 4.80E+06 3.50E+02 1.4E+05 1.10E+10

1997 1.70E+07 9.0E+05 2.00E+10

1998 3.80E+06 3.3E+06 7.80E+09

1999 2.30E+06 2.5E+03 3.00E+08

2000 2.90E+06 9.3E+05 6.90E+08

2001 6.37E+06 1.1E+06 5.90E+09

2002

2003

ATTACHMENT A

SOURCE EMISSIONS

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Table A-21. Estimated source emissions from TA-54 (μCi/yr).

Year Pu U

1943–1976 No source estimates for these years

1977 3.00E-03

1978 2.60E-02

1979 1.30E-02

1980 3.00E-03

1981 1.00E-02

1982 2.00E-02

1983 2.00E-03

1984 2.30E-02

1985 6.00E-03

1986 1.65E-01

1987 2.60E-02

1988 1.40E-02

1989 2.20E-02

1990 8.40E-02

1991 4.50E-02

1992 1.00E-02

1993 <MDA

1994 1.00E-02

1995 8.48E-04

1996

1997 2.80E-02

1998–2001 No source estimates for these years

2002

2003

ATTACHMENT A

SOURCE EMISSIONS

Page 15 of 16
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Table A-22. Estimated source emissions from TA-55 (μCi/yr).

Year Am-241 H-3 Pu Th-232 U

1943–1977 No source estimates for these years

1978 3.99E-01

1979 1.08E-01

1980 2.94E-01

1981 9.70E-02

1982 1.87E+07 2.59E+00

1983 4.42E+07 1.07E+00

1984 1.52E+08 1.04E+00

1985 1.07E+00

1986 1.01E+09 2.34E-01

1987 8.54E+07 2.45E-01

1988 3.14E+08 1.53E+01

1989 2.66E+08 2.22E+00

1990 1.67E+08 4.68E-01

1991 9.12E+07 2.00E+00

1992 1.02E+08 1.12E+00

1993 6.46E+07 1.70E-01

1994 2.26E+07 1.20E-01

1995 5.45E-03 1.56E+07 1.63E-02

1996 3.10E-02 3.10E+07 8.85E-02 5.50E-02

1997 1.20E+07 1.10E-01 4.40E-02

1998 3.80E-03 1.20E+07 6.20E-02 3.00E-02

1999 5.40E-02 1.80E+06 6.30E-02 7.10E-02

2000 3.30E-01 6.40E+06 2.50E+00

2001 6.20E-03 3.30E+06 4.30E-02 1.50E-01 1.70E-01

2002

2003

ATTACHMENT A

SOURCE EMISSIONS

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Table B-1 presents results of a screening analysis to identify radionuclides of potential significance to 

inhalation dose. The analysis, described in Section 4.2.1.2, evaluated the potential 50-year effective 

committed inhalation dose that would be associated with the maximum annual reported emission of 

each radionuclide from data in Tables A-1 through A-22. Inhalation doses were calculated by 

estimating maximum air concentrations using a screening-level dispersion model and assuming an 

annual inhalation rate of 3,400 m3

/yr and maximum effective dose factors from the CD1 compilation 

for ICRP 68 (ICRP 2001). An AMAD of 5 μm was assumed for all airborne particulates. For 

elements, or groups of elements, for which specific isotopes were not specified (i.e., plutonium, 

uranium, MFPs, and P/VAPs), a representative dose factor was selected that maximized the dose 

calculations for that group. 

 Table B-1. Results of screening analysis to identify 

 potentially significant contributors to inhalation dose.

Year

Maximum total 

effective dose (Sv/yr)

Radionuclides contributing 

to ≥95% of dose

1944 2.98E-02 140La, U

1945 5.05E-01 140La, Pu

1946 5.89E-01 140La, Pu

1947 7.18E-01 140La, Pu

1948 3.87E-01 140La, Pu, U

1949 7.66E-01 140La, Pu, U

1950 9.51E-01 140La, Pu, U

1951 2.08E-01 Pu, U

1952 3.39E-01 140La, Pu, U

1953 1.95E-01 140La, Pu, U

1954 4.92E-01 140La, U

1955 1.04E+00 140La, U

1956 8.88E-01 140La, U

1957 5.26E-01 140La, Pu, U

1958 3.53E-01 140La, Pu, U

1959 3.15E-01 140La, Pu, U

1960 2.06E-01 140La, Pu, U

1961 6.12E-01 140La, U

1962 3.43E-01 140La, U

1963 5.20E-02 Pu, U

1964 6.40E-02 Pu, U

1965 6.02E-02 Pu, U

1966 9.68E-02 U

1967 8.33E+02 232Th

1968 8.33E+02 232Th

1969 4.83E-02 Pu, U

1970 4.36E-02 3H, Pu, U

1971 5.60E-02 Pu, U

1972 2.04E-02 Pu, U

1973 4.31E-04 3H, Pu, U

1974 2.27E-03 3H, Pu

1975 1.16E-03 3H, Pu, U

1976 5.33E-04 3H, U

1977 9.63E-03 3H

1978 4.66E-03 3H

1979 7.73E-03 3H, Pu

ATTACHMENT B

SCREENING ESTIMATES

Page 1 of 2
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 72 of 96

Year

Maximum total 

effective dose (Sv/yr)

Radionuclides contributing 

to ≥95% of dose

1980 2.21E-03 3H, Pu

1981 1.69E-03 3H, U

1982 2.80E-02 3H, P/VAP

1983 3.54E-01 P/VAP

1984 3.36E-01 P/VAP

1985 1.41E-03 3H, Pu

1986 1.89E-03 3H, Pu

1987 4.01E-04 3H, P/VAP, Pu, U

1988 2.24E-03 3H

1989 3.36E-03 3H, MFP

1990 1.19E-03 3H

1991 1.06E-03 3H, P/VAP

1992 4.37E-04 3H, P/VAP, U

1993 1.97E-03 3H, P/VAP, U

1994 9.31E-04 3H, U

1995 4.57E-04 3H, MFP, P/VAP, Pu

ATTACHMENT B

SCREENING ESTIMATES

Page 2 of 2
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Tables C-1 through C-29 provide estimated average air concentrations for TAs at LANL for which 

air-monitoring and/or emissions data were available. Air-monitoring data, when available, formed the 

basis for estimates at each TA. For some TAs, more than one monitoring station was active during 

many years. In these cases, the concentrations were averaged over all stations in the TA. For years 

and locations when monitoring data were not available, an estimate was made based on the 

relationship between source emission rate and air concentration for years when data were available 

(see Section 4.2.1.3). Blank values in these tables indicate no data.

Table C-1. Estimated average air concentrations for 239Pu for 

TA-1 (pCi/m3

).a

Year Pu-239 average air concentration

1943–1944 Not availableb

1945 4.6E-01

1946 5.8E-01

1947 9.3E-01

1948–1975 Not availableb

1976–2003 TA was decontaminated in 1975

a. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3

.

b. Source term estimates or measured air concentrations not available 

during these years.

Table C-2. Estimated average air concentrations for 241Am, 3H, 

239Pu, and 234U for TA-2 (pCi/m3

).

a

Year Am-241 H-3 Pu-239 U-234

1943–1986 Not availableb

1987 2.7E+01 1.0E-06 5.3E-05

1988 7.8E+01 2.3E-05 7.1E-05

1989 2.3E+01 2.2E-06 1.0E-04

1990 1.1E+01 1.3E-06 3.7E-05

1991 5.2E+00 5.0E-07 7.5E-05

1992 4.3E+00 1.5E-06 3.7E-05

1993 2.5E+00 6.4E-06 2.7E-05

1994 4.2E+00 3.1E-06 1.7E-05

1995 5.2E-06 3.4E+00 6.2E-06 4.2E-05

1996 Not availableb

2000 0.00E+00 1.8E+00 1.5E-06 1.8E-05

2001–2003 Not availableb

a. From AIRNET database of summarized measured concentrations for 

TA-2, averaged over results reported at locations within the TA (LANL 

2003). 

b. Source term estimates or measured air concentrations not available 

during these years.

ATTACHMENT C

AIR CONCENTRATIONS

Page 1 of 24
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 74 of 96

Table C-3. Estimated average air concentrations for 241Am, 3H, 131I, 239Pu, 232Th, 234U, MFP, and 

P/VAP for TA-3 (pCi/m3

).

a

Year Am-241 H-3 I-131 Pu-239 Th-232 U-234 MFP P/VAP

1943–1951 Not availableb

1952 2.2E-05c

1953 5.1E-04c

1954 2.9E-03c

1955 4.2E-03c

1956 3.3E-03c

1957 2.5E-03c

1958 7.1E-03c

1959 2.0E-03c

1960 6.5E-03c

1961 4.2E-03c

1962 4.0E-03c

1963 1.4E+00c 1.9E-03c

1964 6.5E-01c 1.4E-03c

1965 8.4E-01c 3.5E-03c

1966 4.1E-03c

1967 9.2E-03c

1968 1.3E-02c

1969 2.6E-02c

1970 3.0E-02c

1971 2.0E+02 1.0E-02 2.8E-04 2.6E-04

1972 3.2E-05 3.3E+01 1.6E-02c 1.4E-04 7.8E-05

1973 7.0E-06 3.5E+01 9.3E-03c 1.4E-04 3.4E-05c 1.6E-04 2.8E-02c

1974 1.0E-02c 3.2E-03c 4.4E-04c 7.5E-04c

1975 4.8E+01 3.0E-03c 9.2E-04c 4.3E-04c 4.0E-04c

1976 6.6E-04c 8.7E-05c 8.0E-04c 9.1E-04c

1977 8.8E+02c 1.9E-04c 7.4E-05c 7.4E-04c 1.1E-03c

1978 2.2E+02c 1.8E-04c 1.3E-04c 4.1E-04c 8.9E-04c

1979 6.6E+03c 3.5E-04c 2.4E-03c 5.7E-04c 1.0E-03c

1980 1.0E+01c 2.1E-04c 1.6E-03c 3.4E-04c 9.3E-04c

1981 2.0E+03c 9.7E-05c 8.7E-05c 5.2E-04c 3.8E-04c

1982 4.3E+03c 1.7E-03c 1.6E-04c 7.1E-04c 1.7E-04c

1983 5.0E+03c 1.8E-04c 1.9E-04c 4.0E-04c 3.8E-05c

1984 3.9E+03c 1.6E-04c 2.5E-04c 4.7E-04c 9.1E-05c

1985 4.7E+03c 3.2E-04c 4.3E-04c 7.6E-04c 7.6E-05c

1986 2.7E+03c 8.4E-05c 4.3E-04c 1.4E-03c 1.1E-04c

1987 1.9E+03c 1.4E-04c 1.9E-03c 4.8E-05c

1988 1.8E+04c 1.1E-04c 1.1E-03c 6.5E-05c

1989 6.4E+02c 8.6E-05c 8.0E-04c 8.4E-05c

1990 1.1E+03c 4.8E-05c 4.3E-04c 8.6E-05c

1991 1.5E-06 1.5E+01 1.2E-06 9.3E-05 3.1E-05c

1992 3.2E-06 2.7E+01 2.5E-06 3.6E-05 1.9E-05c

1993 1.9E-05 5.3E+00 5.6E-05 1.4E-05 1.3E-05c

1994 5.8E-06 2.0E+00 3.2E-06 3.7E-05 8.4E-05c

1995 1.4E-05 6.0E+00 2.9E-06 2.0E-05 2.1E-03c 2.1E-03c

1996 1.5E-06 1.3E+00 2.7E-06 3.6E-07c 2.3E-05

1997 2.5E-06 3.6E+00 2.7E-06 8.4E-07c 1.7E-05

1998 3.5E-06 2.7E+00 4.0E-07 9.2E-07c 1.5E-05 1.5E-05c

ATTACHMENT C

AIR CONCENTRATIONS

Page 2 of 24
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 75 of 96

Year Am-241 H-3 I-131 Pu-239 Th-232 U-234 MFP P/VAP

1999 2.2E-06 2.7E+00 2.7E-06 4.8E-07c 1.9E-05

2000 0.0E+00 2.4E+00 2.6E-06 2.9E-07c 3.0E-05

2001 0.0E+00 3.1E+00 6.0E-07 3.1E-07c 2.7E-05

2002–2003 Not availableb

a. From AIRNET database of summarized measured concentrations for TA-3, averaged over results reported at locations 

in the TA (LANL 2003), unless otherwise indicated. 

b. Source term estimates or measured air concentrations not available during these years.

c. Based on estimated average ratio of plutonium activity:source emission activity for TA-3 of 2.2 × 10-12 yr/m3

.

Table C-4. Estimated average air concentrations for 241Am, 

3

H, 239Pu, and 234U for TA-5 (pCi/m3).

a

Year Am-241 H-3 Pu-239 U-234

1943–1972 Not availableb

1973 1.0E+02 1.9E-05 4.7E-04

1974 8.1E+01 2.4E-05 1.6E-04

1975 1.7E+02 2.2E-05 1.1E-04

1976 1.2E+02 4.9E-06 9.5E-05

1977 5.7E+01 2.2E-05 1.3E-04

1978 1.6E+01 2.9E-05 9.5E-05

1979 1.5E+01 8.4E-06 1.2E-04

1980 1.7E+01 1.0E-06 8.7E-05

1981 4.4E+00 6.1E-06 6.5E-05

1982 2.5E+01 1.5E-06 6.5E-05

1983 1.7E+01 3.1E-06 7.4E-05

1984 1.8E+01 1.3E-06 5.7E-05

1985 1.2E+01 0.0E+00 5.0E-05

1986 9.8E+00 1.0E-06 4.1E-05

1987 1.9E+01 2.0E-07 6.1E-05

1988 1.5E+01 2.0E-07 1.1E-04

1989 3.5E+00 4.0E-07 1.2E-04

1990 3.2E+00 1.8E-06 5.0E-05

1991 3.7E+00 7.0E-07 8.6E-05

1992 1.4E-06 4.4E+00 8.0E-07 3.4E-05

1993 2.6E+00 1.5E-06 3.5E-05

1994 1.5E+00 1.2E-06 3.5E-05

1995 3.4E-06 2.4E+00 4.4E-06 4.8E-05

1996 2.5E-06 1.1E+00 1.2E-06 5.6E-05

1997 2.4E-06 5.5E+00 5.0E-07 2.4E-05

1998 2.0E-06 3.3E+01 1.0E-06 2.4E-05

1999 3.6E-06 2.2E+00 2.0E-07 2.1E-05

2000 3.0E-07 2.7E+00 2.0E-06 5.4E-05

2001 0.0E+00 4.2E+00 0.0E+00 3.4E-05

2002–2003 Not availableb

a. From AIRNET database of summarized measured concentrations for 

TA-3, averaged over results reported at locations in the TA (LANL 

2003). 

b. Source term estimates or measured air concentrations not available 

during these years.

ATTACHMENT C

AIR CONCENTRATIONS

Page 3 of 24
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 76 of 96

Table C-5. Estimated average air concentrations for 241Am, 

3

H, 239Pu, and 234U for TA-6 (pCi/m3).

a

Year Am-241 H-3 Pu-239 U-234

1943–1970 Not availableb

1971 3.6E+01 4.1E-05 3.7E-04

1972 2.9E+01 1.5E-04 9.3E-05

1973

1974 1.6E+01 2.6E-05 7.8E-05

1975 1.1E-05 2.2E+01 5.5E-05 4.2E-05

1976 2.5E+01 3.9E-06 9.1E-05

1977 3.0E-07 2.5E+01 1.7E-05 2.6E-04

1978 3.0E-07 5.0E+00 2.7E-05 1.1E-04

1979 0.0E+00 2.8E+00 3.3E-06 5.1E-05

1980 1.0E-07 3.8E+00 2.6E-06 4.3E-05

1981 4.5E-05 6.7E+00 5.7E-06 5.0E-05

1982 2.0E-07 1.1E+01 1.2E-06 4.8E-05

1983 1.1E+01 1.2E-06 5.3E-05

1984 4.4E+00 1.2E-06 3.1E-05

1985 8.3E+00 1.9E-06 6.0E-05

1986 3.1E-06 3.6E+00 1.2E-06 5.8E-05

1987 1.5E-06 1.1E+01 6.0E-07 6.2E-05

1988 6.4E-06 9.4E+00 7.0E-07 8.1E-05

1989 2.8E-06 2.3E+00 4.6E-06 1.0E-04

1990 1.6E-06 1.4E+00 2.1E-06 7.2E-05

1991 9.0E-07 1.6E+00 1.0E-06 8.3E-05

1992 4.5E-06 2.7E+00 1.7E-06 2.7E-05

1993 1.5E-06 3.3E+00 2.2E-06 2.2E-05

1994 4.1E-06 1.3E+00 8.0E-07 2.8E-05

1995 5.7E-06 3.6E+00 1.2E-05 2.1E-05

1996 0.0E+00

1997–2003 Not availableb

a. From AIRNET database of summarized measured concentrations for 

TA-3, averaged over results reported at locations within the TA (LANL 

2003). 

b. Source term estimates or measured air concentrations not available 

during these years.

ATTACHMENT C

AIR CONCENTRATIONS

Page 4 of 24
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Table C-6. Estimated average air concentrations for 3H for 

TA-9 (pCi/m3

).

a

Year H-3

1943–1971 Not availableb

1972 1.5E+03

1973 7.9E+01

1974 2.9E+00

1975 Not availableb

1976 2.8E+02

1977 5.7E+01

1978 5.7E+00

1979 1.1E+01

1980 1.1E+01

1981–2003 Not availableb

a. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3

.

b. Source term estimates or measured air concentrations not available 

during these years.

Table C-7. Estimated average air concentrations for 234U for 

TA-10 (pCi/m3).

a

Year U-234

1943 Not availableb

1944 2.2E-02

1945 2.2E-02

1946 6.6E-02

1947 8.8E-02

1948 1.3E-01

1949 2.2E-01

1950 1.1E+00

1951 4.4E-01

1952 4.4E-01

1953 4.4E-01

1954 8.8E-03

1955 7.3E-02

1956 7.7E-02

1957 2.4E-02

1958 1.5E-02

1959 2.6E-02

1960 1.5E-02

1961 1.9E+00

1962 4.0E-01

1963 1.1E-01

1964–2003 Not availableb

a. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3

.

b. Source term estimates or measured air concentrations not available 

during these years.

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AIR CONCENTRATIONS

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Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 78 of 96

Table C-8. Estimated average air concentrations for 241Am, 

3

H, 239Pu, and 234U for TA-11 (pCi/m3).

a

Year Am-241 H-3 Pu-239 U-234

1943–1970 Not availableb

1971 4.2E+01 4.7E-05 1.4E-04

1972 3.3E-05 2.4E+01 4.8E-05 9.3E-05

1973 1.3E+01 2.3E-05 1.6E-04

1974–2003 Not availableb

a. From AIRNET database of summarized measured concentrations for 

TA-3, averaged over results reported at locations within the TA (LANL 

2003). 

b. Source term estimates or measured air concentrations not available 

during these years.

Table C-9. Estimated average air concentrations for 241Am, 3H, 239Pu, 

232Th, and 234U for TA-15 (pCi/m3

).

a

Year Am-241 H-3 Pu-239 Th-232 U-234

1944 1.3E-01b

1945 2.6E-01b

1946 5.3E-01b

1947 7.9E-01b

1948 1.2E+00b

1949 1.9E+00b

1950 9.9E+00b

1951 4.4E+00b

1952 4.0E+00b

1953 3.5E+00b

1954 3.3E+00b

1955 2.6E+00b

1956 1.7E+00b

1957 2.6E+00b

1958 2.4E+00b

1959 1.1E+00b

1960 1.6E+00b

1961 7.7E-01b

1962 1.0E+00b

1963 8.7E-01b

1964 1.3E+00b

1965 1.3E+00b

1966 2.1E+00b

1967 7.9E+03b 4.4E+03b 1.6E+00b

1968 9.9E+03b 4.4E+03b 1.2E+00b

1969 9.9E+03b 9.4E-01b

1970 6.3E+04b 6.8E-01b

1971 8.2E+01 4.2E-05 7.0E-04

1972 2.2E-05 2.8E+01 5.1E-05 9.3E-05

1973 2.0E-06 2.1E+01 1.6E-05 3.1E-04

1974–1977 Not availablec

1978 1.6E+02b

1979–1991 Not availablec

1992 5.0E-03b

1993 1.1E+00 1.1E-02b

ATTACHMENT C

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Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 79 of 96

Year Am-241 H-3 Pu-239 Th-232 U-234

1994 2.0E+00 4.0E-07 6.7E-05

1995 5.1E-06 1.8E+00 3.7E-06 1.4E-05

1996 2.3E-06 1.1E+00 1.4E-06 5.2E-05

1997 2.0E-06 1.9E+00 6.5E-07 2.9E-05

1998 2.2E-06 2.1E+00 8.0E-07 1.4E-05

1999 2.3E-06 1.7E+00 8.0E-07 1.9E-05

2000 4.0E-07 1.8E+00 5.0E-08 2.7E-05

2001 2.5E-07 2.3E+00 0.0E+00 6.6E-05

2002 2.0E-08 2.8E+00 0.0E+00 3.8E-05

2003 Not availablec

a. From AIRNET database of summarized measured concentrations for TA-15, averaged 

over results reported at locations within the TA (LANL 2003), unless otherwise indicated.

b. Based on estimated average ratio of plutonium activity:source emission activity for TA-3 

and TA-21 of 2.2 × 10-12 yr/m3

.

c. Source term estimates or measured air concentrations not available during these years.

Table C-10. Estimated average air concentrations for 241Am, 3H, 131I, 

239Pu, and 234U for TA-16 (pCi/m3

).

a

Year Am-241 H-3 I-131 Pu-239 U-234

1943–1953 Not availableb

1954 8.4E-02c

1955

1956

1957 3.1E-02c

1958

1959 2.2E-03c

1960 1.1E-01c

1961

1962

1963 1.1E-01c

1964 6.6E-03c

1965 8.8E-03c

1966

1967 1.1E-02c

1968 8.6E-02c

1969 6.6E-03c

1970 2.4E-02c

1971 4.5E+01 1.0E-02 6.1E-05 3.2E-04

1972 4.0E-05 3.1E+01 5.7E-05 9.3E-05

1973 3.0E-06 1.6E+01 2.8E-05 1.6E-04

1974 1.2E+01 3.0E-05 1.1E-04

1975 4.0E-06 1.8E+01 1.9E-05 4.0E-05

1976 2.0E+01 4.7E-06 5.4E-05

1977 0.0E+00 3.0E+01 1.9E-05 4.3E-04

1978 0.0E+00 6.0E+00 3.6E-05 7.4E-05

1979 0.0E+00 2.2E+00 2.0E-05 4.0E-05

1980 0.0E+00 1.1E+01 1.1E-06 4.7E-05

1981 1.9E-06 1.9E+00 3.6E-06 3.6E-05

1982 3.0E-07 1.0E+01 1.0E-06 3.6E-05

1983 1.1E+01 5.5E-07 3.6E-05

1984 1.3E+01 0.0E+00 2.0E-05

ATTACHMENT C

AIR CONCENTRATIONS

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Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 80 of 96

Year Am-241 H-3 I-131 Pu-239 U-234

1985 9.5E+00 3.9E-06 4.3E-05

1986 2.7E-06 4.7E+00 6.0E-07 2.1E-05

1987 1.0E-06 9.9E+00 7.5E-07 2.9E-05

1988 1.9E-06 4.3E+00 8.5E-07 5.3E-05

1989 2.4E-06 2.7E+00 6.0E-07 9.1E-05

1990 2.8E-06 1.1E+00 1.6E-06 5.2E-05

1991 1.2E-06 5.0E-01 1.0E-06 6.1E-05

1992 1.1E-06 1.6E+00 6.0E-06 2.8E-05

1993 9.0E-01 5.0E-07 1.9E-05

1994 9.1E+00 0.0E+00 2.6E-05

1995 4.6E-06 1.8E+02 3.3E-06 1.9E-05

1996 1.8E-06 2.4E+01 4.0E-07 2.7E-05

1997 2.2E-06 6.2E+01 8.0E-07 1.9E-05

1998 2.6E-06 2.5E+02 9.0E-07 2.9E-05

1999 3.2E-06 5.5E+01 1.2E-06 1.5E-05

2000 0.0E+00 6.1E+01 0.0E+00 1.4E-05

2001 2.0E-07 6.8E+01 0.0E+00 1.9E-05

2002–2003 Not availableb

a. From AIRNET database of summarized measured concentrations for TA-16, averaged over 

results reported at locations within the TA (LANL 2003), unless otherwise indicated.

b. Source term estimates or measured air concentrations not available during these years.

c. Based on estimated average ratio of plutonium activity:source emission activity for TA-3 and 

TA-21 of 2.2 × 10-12 yr/m3

.

Table C-11. Estimated average air concentrations for 234U for 

TA-18 (pCi/m3

).

a

Year U-234

1943–1978 Not availableb

1979 8.7E-06

1980–2003 Not availableb

a. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3

.

b. Source term estimates or measured air concentrations not available 

during these years.

Table C-12. Estimated average air concentrations for 241Am, 3H, 131I, 239Pu, 234U, 

and MFP for TA-21 (pCi/m3

).

a

Year Am-241 H-3 I-131 Pu-239 U-234 MFP

1943–1947 Not availableb

1948 3.4E-01c

1949 3.4E-01c

1950 4.1E-01c

1951 5.9E-02c

1952 1.3E-01c

1953 7.7E-02c

1954 4.8E-02c

1955 1.9E-01c

1956 1.7E-01c

1957 1.6E-01c

1958 1.8E-01c

1959 4.1E-01c

1960 7.8E-02c

ATTACHMENT C

AIR CONCENTRATIONS

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Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 81 of 96

Year Am-241 H-3 I-131 Pu-239 U-234 MFP

1961 1.4E-02c

1962 1.8E-02c 1.4E-02c

1963 6.3E-02c 6.7E-02c

1964 2.7E-02c 5.1E-03c

1965 2.0E-02c 2.0E-02c

1966 2.3E-02c 2.2E-02c

1967 2.2E-02c 1.5E-02c

1968 4.3E-03c 2.9E-03c

1969 9.2E-03c 7.8E-03c

1970 6.2E-03c 2.3E-03c

1971 8.5E+01 2.9E-05 1.2E-04

1972 3.6E+01 8.4E-05 1.1E-04

1973 1.5E+02 2.3E-05 1.6E-04 2.2E-06c

1974 6.8E+01 2.4E-05 7.8E-05 6.4E-06c

1975 6.4E+01 1.8E-05 4.8E-05 3.2E-06c

1976 4.0E+01 7.6E-06 6.5E-05 1.2E-06c

1977 5.2E+01 2.1E-05 1.5E-04 7.2E-06c

1978 7.5E-08c 2.3E+01 2.3E-05 1.5E-04 2.3E-06c

1979 4.2E-08c 3.8E+00 6.1E-06 1.3E-04 1.0E-06c

1980 1.3E-07c 1.1E+01 3.1E-05 1.1E-04 9.2E-06c

1981 6.4E-08c 5.6E+00 4.6E-06 5.6E-05 6.2E-06c

1982 7.7E-08c 1.6E+01 6.0E-06 1.5E-04 9.6E-07c

1983 2.1E-07c 2.0E+01 9.0E-07 4.8E-05 1.7E-06c

1984 8.8E+00 1.5E-06 1.0E-04 6.9E-07c

1985 1.6E+01 4.0E-07 6.6E-05 7.9E-07c

1986 1.6E+01 1.4E-06 5.4E-05 7.1E-07c

1987 5.2E+01 1.1E-06 5.4E-05 4.1E-07c

1988 4.0E+01 8.0E-07 8.1E-05 3.4E-07c

1989 1.7E+01 1.3E-06 1.3E-04 6.8E-08c

1990 1.3E+01 2.2E-06 7.6E-05 2.9E-08c

1991 0.0E+00 8.5E+00 1.9E-06 8.4E-05 6.6E-08c

1992 2.7E-06 9.4E+00 1.0E+00 2.5E-06 3.8E-05 5.3E-08c

1993 3.6E-06 4.2E+00 4.9E-06 2.8E-05 2.2E-08c

1994 6.4E-06 3.4E+00 6.6E-06 2.8E-05 1.1E-07c

1995 6.2E-06 8.0E+00 1.2E-05 3.2E-05

1996 4.2E-06 3.1E+00 1.7E-05 2.5E-04

1997 4.3E-06 4.8E+00 1.7E-05 2.1E-05

1998 5.6E-06 1.1E+01 2.6E-05 1.6E-05

1999 2.9E-06 6.1E+00 3.5E-06 2.2E-05

2000 9.3E-07 7.3E+00 3.7E-06 2.0E-05

2001 0.0E+00 7.2E+00 3.7E-06 2.6E-05

2002–2003 Not availableb

a. From AIRNET database of summarized measured concentrations for TA-21, averaged over 

results reported at locations within the TA (LANL 2003), unless otherwise indicated.

b. Source term estimates or measured air concentrations not available during these years.

c. Based on estimated average ratio of plutonium activity:source emission activity for TA-21 of 

2.28 × 10-12 yr/m3

.

ATTACHMENT C

AIR CONCENTRATIONS

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Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 82 of 96

Table C-13. Estimated average air concentrations for 241Am, 3H, 131I, 

239Pu, and 234U for TA-33 (pCi/m3

).

a

Year Am-241 H-3 I-131 Pu-239 U-234

1943–1965 Not availableb

1966 2.2E-02c

1967–1870 Not availableb

1971 5.0E+02 1.0E-02 8.3E-05 1.2E-04

1972 1.8E+02 5.5E-05 1.4E-04

1973 6.0E+01 1.7E-05 3.1E-04

1974 1.4E+02 2.8E-05 1.1E-04

1975 1.6E+02 2.3E-05 3.9E-05

1976 5.9E+01 5.3E-06 6.4E-05

1977 8.0E+00 1.8E-05 1.2E-04

1978 2.5E+01 2.8E-05 9.5E-05

1979 4.0E+01 6.9E-06 6.0E-05

1980 4.4E+01 3.5E-06 7.0E-05

1981 3.0E+01 3.9E-06 5.6E-05

1982 8.8E+01 2.4E-06 5.7E-05

1983 3.6E+01 0.0E+00 3.3E-05

1984 5.6E+01 7.0E-06 2.8E-05

1985 1.1E+02 0.0E+00 3.0E-05

1986 3.1E+01 6.0E-07 2.2E-05

1987 2.0E+01 8.0E-07 5.1E-05

1988 5.8E+01 4.0E-07 1.5E-04

1989 1.8E+01 0.0E+00 8.2E-05

1990 7.9E+00 7.3E-06 8.7E-05

1991 3.2E+00 7.0E-07 1.9E-05

1992 3.7E+00 9.0E-07 1.5E-05

1993 3.0E+00 1.8E-06 1.6E-05

1994 1.8E+00 5.0E-07 1.5E-05

1995 3.9E-06 3.5E+00 1.5E-05 1.7E-05

1996 1.4E+00

1997 3.1E-06 9.0E-01 1.4E-06 1.3E-05

1998 2.4E-06 1.3E+00 1.4E-06 1.5E-05

1999 2.5E-06 4.0E+00 1.2E-06 2.0E-05

2000 0.0E+00 3.4E+00 2.0E-07 1.1E-05

2001 3.3E+00 0.0E+00 1.4E-05

2002–2003

a. From AIRNET database of summarized measured concentrations for TA-33, 

averaged over results reported at locations within the TA (LANL 2003), unless 

otherwise indicated.

b. Source term estimates or measured air concentrations not available during these 

years.

c. Based on estimated average ratio of plutonium activity:source emission activity for 

TA-3 and TA-21 of 2.2 × 10-12 yr/m3

.

ATTACHMENT C

AIR CONCENTRATIONS

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Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 83 of 96

Table C-14. Estimated average air concentrations for 241Am, 3H, 239Pu, 234U, 

MFP, and P/VAP for TA-35 (pCi/m3

).

a

Year Am-241 H-3 Pu-239 U-234 MFP P/VAP

1943–1966 Not availableb

1967 1.5E-05

1968 1.3E-05

1969 1.2E-05

1970 9.3E-06

1971 6.9E+03 1.6E-05

1972 5.5E+03 3.9E-05

1973 2.7E+03 5.2E-06

1974 3.1E+03 1.8E-05

1975 5.3E+03 1.3E-05

1976 3.7E+03 5.2E-06

1977 1.7E+03 1.8E-06

1978 1.5E+03 4.3E-06

1979 2.9E+03 1.6E-05

1980 5.5E+01 4.6E-07

1981 5.9E-07

1982 2.9E-06

1983 1.3E+01 2.0E-06

1984 4.5E+02 9.2E-07

1985 1.2E+01 1.2E-06

1986 1.0E+02 8.0E-07

1987 3.4E+02 1.4E-06

1988 2.6E+02 3.8E-07

1989 4.0E+01 1.5E-06

1990 8.8E-02 2.0E-06

1991 9.5E-06 2.7E-06

1992 2.2E-01 7.9E-07

1993 5.9E-07

1994 8.6E-07

1995 7.8E-08 6.5E-07 1.5E-06 3.6E-06 3.6E-06

1996–2003 Not availableb

a. Based on estimated average ratio of plutonium activity:source emission activity for TA-3 and 

TA-21 of 2.2 × 10-12 yr/m3

.

b. Source term estimates or measured air concentrations not available during these years.

ATTACHMENT C

AIR CONCENTRATIONS

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Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 84 of 96

Table C-15. Estimated average air concentrations for 241Am, 

3

H, 239Pu, and 234U for TA-36 (pCi/m3).

a

Year Am-241 H-3 Pu-239 U-234

1943–1957 Not availableb

1958 9.5E-02c

1959 1.8E-02c

1960 3.1E-02c

1961 Not availableb

1962 2.2E-02c

1963 3.1E-02c

1964 8.8E-03c

1965 4.4E-02c

1966 6.2E-02c

1967 1.1E-01c

1968 5.9E-02c

1969 4.2E-02c

1970 1.3E-02c

1971 3.8E+01 2.7E-05 9.5E-02

1972 2.9E+01 5.7E-05 1.8E-02

1973 2.9E+01 2.2E-05 3.1E-02

1974–1992 Not availableb

1993 1.1E+00

1994 1.3E+00 1.2E-05 7.0E-05

1995 4.6E-06 3.7E+00 1.1E-05 9.0E-05

1996 1.5E-06 1.1E+00 8.0E-07 4.9E-05

1997 2.0E-06 1.4E+00 6.5E-07 3.8E-05

1998 2.1E-06 1.8E+00 2.5E-07 3.5E-05

1999 3.6E-06 1.7E+00 4.5E-07 3.5E-05

2000 5.0E-07 1.6E+00 1.5E-07 3.3E-05

2001 0.0E+00 2.5E+00 0.0E+00 1.5E-04

2002 2.0E-08 2.8E+00 0.0E+00 3.8E-05

2003 Not availableb

a. From AIRNET database of summarized measured concentrations for 

TA-36, averaged over results reported at locations within the TA (LANL 

2003), unless otherwise indicated.

b. Source term estimates or measured air concentrations not available 

during these years.

c. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3

.

ATTACHMENT C

AIR CONCENTRATIONS

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Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 85 of 96

Table C-16. Estimated average air concentrations for 3H, 

239Pu, and 234U for TA-39 (pCi/m3

).

a

Year H-3 Pu-239 U-234

1943–1953 Not availableb

1954 4.2E-01c

1955 3.3E-01c

1956 3.8E-01c

1957 5.9E-01c

1958 6.3E-01c

1959 4.2E-01c

1960 2.6E-01c

1961 3.6E-01c

1962 3.6E-01c

1963 2.8E-01c

1964 2.5E-01c

1965 2.4E-01c

1966 2.7E-01c

1967 4.4E-01c

1968 1.1E-01c

1969 1.5E-01c

1970 1.1E-01c

1971 1.9E-01c

1972 2.4E-01c

1973–1976 Not availableb

1977 3.9E+01 1.0E-07 1.2E-04

1978 1.5E+01 3.5E-05 1.3E-04

1979 1.6E+01 3.7E-06 4.0E-05

1980 2.8E+01 4.4E-06 7.3E-05

1981 1.2E+01 2.0E-06 4.8E-05

1982 1.5E+02 2.7E-06 8.4E-05

1983 3.1E+01 1.8E-06 1.6E-05

1984 1.4E+01 0.0E+00 3.6E-05

1985 4.2E+01 0.0E+00 5.1E-05

1986 2.5E+01 1.5E-06 3.0E-05

1987–2003 Not availableb

a. From AIRNET database of summarized measured concentrations for 

TA-39, averaged over results reported at locations within the TA (LANL 

2003), unless otherwise indicated.

b. Source term estimates or measured air concentrations not available 

during these years.

c. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3

.

ATTACHMENT C

AIR CONCENTRATIONS

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Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 86 of 96

Table C-17. Estimated average air concentrations for 3H, 

239Pu, and 234U for TA-41 (pCi/m3

).

a

Year H-3 Pu-239 U-234

1943–1966 Not availableb

1967 2.64E-04

1968 7.26E-05

1969 1.98E-05

1970 1.72E-05

1971 7.0E+02 4.18E-05

1972 2.4E+02 2.42E-05

1973 1.3E+02 3.34E-06

1974–1978 Not availableb

1979 3.1E+02

1980 9.1E+02

1981 2.8E+02

1982 2.9E+02

1983 2.1E+03

1984 1.1E+04

1985 2.8E+03

1986 2.9E+03

1987 1.0E+03

1988 3.8E+03

1989 2.6E+04

1990 9.8E+03

1991 8.4E+03

1992 6.4E+02

1993 1.1E+03 2.2E-08

1994 3.8E+02 4.4E-08

1995 1.7E+02 3.4E-08 2.0E-08

1996 2.4E+02

1997 9.2E+01

1998 7.9E+01

1999 2.9E+01

2000 1.4E+01

2001 1.2E+03

2002–2003 Not availableb

a. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3

.

b. Source term estimates or measured air concentrations not available 

during these years.

Table C-18. Estimated average air concentrations for 239Pu for 

TA-42 (pCi/m3

).

a

Year Pu-239

1943–1968 Not availableb

1969 1.8E-03

1970–2003 Not availableb

a. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3

.

b. Source term estimates or measured air concentrations not available 

during these years.

ATTACHMENT C

AIR CONCENTRATIONS

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Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 87 of 96

Table C-19. Estimated average air concentrations for 241Am , 

3

H, 239Pu, and 234U for TA-43 (pCi/m3).

a

Year Am-241 H-3 Pu-239 U-234

1943–1971 Not availableb

1971 4.3E+01 1.1E-04 2.2E-04

1972 2.8E+01 1.0E-04 9.3E-05

1973 1.4E+01 5.2E-05 1.6E-04

1974 1.5E-05c

1975 3.6E-06c

1976 1.7E-05c

1977 1.0E-05c

1978 3.4E-06c

1979 1.7E-06c

1980 4.0E-07c

1981 8.1E-07c

1982 3.1E-06

1983 7.3E-06c

1984 2.3E-06c

1985 4.0E-06c

1986 6.4E-06c

1987 1.1E-06c

1988 3.2E-06c

1989–1994 Not availableb

1995 5.9E-07c 1.2E-06c 2.5E-06c

1996–2003 Not availableb

a. From AIRNET database of summarized measured concentrations for 

TA-43, averaged over results reported at locations in the TA (LANL 

2003), unless otherwise indicated.

b. Source term estimates or measured air concentrations not available 

during these years.

c. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3

.

ATTACHMENT C

AIR CONCENTRATIONS

Page 15 of 24
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 88 of 96

Table C-20. Estimated average air concentrations for 234U for 

TA-46 (pCi/m3

).

a

Year U-234

1943–1970 Not availableb

1971 8.8E-06

1972 2.6E-04

1973 4.8E-06

1974 9.0E-07

1975 1.1E-06

1976 6.8E-07

1977 8.8E-09

1978 5.6E-05

1979 5.0E-06

1980 3.3E-06

1981 3.0E-05

1982 4.5E-06

1983 7.9E-08

1984 1.1E-07

1985 6.2E-08

1986 8.8E-09

1987–2003 Not availableb

a. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3

, unless otherwise 

indicated.

b. Source term estimates or measured air concentrations not available 

during these years.

ATTACHMENT C

AIR CONCENTRATIONS

Page 16 of 24
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 89 of 96

Table C-21. Estimated average air concentrations for 241Am, 239Pu, 

234U, MFP, and P/VAP for TA-48 (pCi/m3

).a

Year Am-241 Pu-239 U-234 MFP P/VAP

1943–1966 Not availableb

1967 2.4E-04

1968 3.3E-04

1969 2.9E-04

1970 1.3E-04

1971 4.2E-05

1972 2.5E-04 1.8E-05

1973 4.4E-05 4.3E-06 2.2E-03

1974 5.3E-05 2.8E-06 2.1E-03

1975 2.7E-05 7.6E-06 1.6E-03

1976 1.1E-05 2.5E-04 2.7E-03

1977 1.8E-05 1.2E-04 4.8E-03

1978 4.2E-06 2.5E-05 2.6E-03

1979 7.4E-07 2.4E-05 2.4E-03

1980 3.5E-06 1.5E-06 3.9E-03

1981 2.9E-06 5.1E-06 3.0E-03

1982 2.2E-05 1.6E-05 2.4E-03

1983 7.3E-06 1.1E-06 1.8E-03

1984 5.6E-06 2.9E-06 3.5E-03

1985 4.6E-06 4.2E-06 2.7E-03

1986 6.3E-06 1.3E-06 5.5E-03

1987 1.4E-06 3.5E-06 2.8E-03

1988 1.6E-06 4.8E-07 2.4E-03

1989 3.3E-06 5.9E-07 9.6E-01

1990 3.3E-06 3.7E-07 2.3E-03

1991 1.3E-06 2.4E-03 2.2E-01

1992 1.5E-05 9.2E-07 6.0E-03 8.3E-02

1993 7.0E-06 3.1E-06 3.0E-03 1.7E-01

1994 7.1E-06 8.8E-07 8.6E-04 1.8E-01

1995 3.8E-06 6.8E-06 1.2E-06 5.8E-02 5.8E-02

1996 1.1E-08 2.4E-08 2.2E-04

1997 7.9E-10 5.5E-09 3.1E-07 4.0E-03

1998 8.1E-10 2.4E-04

1999 1.3E-09 8.6E-03

2000 3.7E-02

2001 5.1E-03

2002–2003 Not availableb

a. Based on estimated average ratio of plutonium activity:source emission activity for 

TA-3 and TA-21 of 2.2 × 10-12 yr/m3

.

b. Source term estimates or measured air concentrations not available during these 

years.

ATTACHMENT C

AIR CONCENTRATIONS

Page 17 of 24
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 90 of 96

Table C-22. Estimated average air concentrations for 241Am, 3H, 131I, 

239Pu, and 234U for TA-49 (pCi/m3

).a

Year Am-241 H-3 I-131 Pu-239 U-234

1943–1970 Not availableb

1971 1.5E+02 1.0E-02 8.4E-05 3.7E-04

1972 2.1E+01 7.6E-05 1.9E-04

1973 3.2E+01 1.9E-05 1.6E-04

1974 2.2E+01 3.2E-05 1.4E-04

1975 1.0E-06 2.1E+01 2.1E-05 4.2E-05

1976 2.2E+01 4.3E-06 8.4E-05

1977 0.0E+00 1.2E+01 1.6E-05 1.7E-04

1978 0.0E+00 5.0E+00 2.6E-05 9.5E-05

1979 0.0E+00 5.4E+00 4.6E-06 6.4E-05

1980 2.2E-06 2.1E+00 6.4E-06 5.9E-05

1981 9.0E-07 4.4E+00 5.9E-06 5.1E-05

1982 0.0E+00 6.9E+00 1.8E-06 7.4E-05

1983 1.1E+01 1.0E-07 1.0E-05

1984 1.3E+01 8.0E-07 2.5E-05

1985 3.6E+01 5.2E-06 3.9E-05

1986 2.5E+00 1.0E-06 3.2E-05

1987 1.2E-06 1.8E+01 6.0E-07 3.1E-05

1988 6.6E-06 9.6E+00 7.0E-07 4.6E-05

1989 2.6E+00 0.0E+00 6.9E-05

1990 1.7E-06 1.1E+00 8.0E-07 4.2E-05

1991 1.1E-06 9.0E-01 1.7E-06 3.6E-05

1992 5.0E-07 1.6E+00 1.3E-05 5.1E-05

1993 1.5E-06 2.4E+00 2.8E-06 3.4E-05

1994 4.6E-06 1.5E+00 2.6E-06 2.1E-05

1995 3.4E-06 2.2E+00 3.1E-06 1.9E-05

1996 4.8E-06 1.7E+00 5.2E-06 2.4E-05

1997 2.1E-06 3.5E+00 6.0E-07 8.6E-06

1998 3.2E-06 6.7E+00 1.3E-06 1.8E-05

1999 2.8E-06 3.4E+00 4.5E-07 1.8E-05

2000 1.5E-05 3.6E+00 2.0E-07 1.3E-05

2001–2003 Not availableb

a. From AIRNET database of summarized measured concentrations for TA-49, 

averaged over results reported at locations in the TA (LANL 2003). 

b. Source term estimates or measured air concentrations not available during these 

years.

ATTACHMENT C

AIR CONCENTRATIONS

Page 18 of 24
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 91 of 96

Table C-23. Estimated average air concentrations for 241Am, 3H, 131I, 239Pu, 232Th, 234U, 

and MFP for TA-50 (pCi/m3

).a

Year Am-241 H-3 I-131 Pu-239 Th-232 U-234 MFP

1943–1966 Not availableb

1967 2.2E-04c

1968 1.5E-04c

1969 9.2E-05c

1970 4.5E-05c

1971 6.3E+02 1.0E-02 3.5E-05c

1972 6.0E-05c

1973 5.5E-06c 3.8E-05c

1974 8.6E-06c 2.1E-04c

1975 9.0E-06c 1.0E-04c

1976 2.4E-06c 6.5E-05c

1977 1.5E-04c 2.0E-04c

1978 3.8E-05c 9.5E-05c

1979 6.4E-06c 2.5E-05c

1980 2.6E-06c 2.0E-05c

1981 3.9E-06c 5.8E-05

1982 1.4E-05c 3.5E-05c

1983 1.2E-05c 2.2E-05

1984 8.1E-06c 2.1E-05c

1985 4.4E-06c 2.0E-05c

1986 6.3E-06c 4.8E-05c

1987 9.9E-06c 5.1E-05c

1988 4.5E-06c 3.3E-05c

1989 1.0E-06c 2.3E-05c

1990 3.3E-07c 9.3E-06c

1991 3.0E-06c 7.4E-06c

1992 1.2E-06c 8.5E-06c

1993 6.2E-07c 8.9E-06c

1994 6.8E-07c 1.6E-05c

1995 1.4E-07c 1.6E-06c

1996 2.4E-08c 9.2E-08c 4.2E-07c

1997 1.8E-08c 1.2E-07c 2.9E-09c

1998 1.4E-08c 3.3E-08c 1.7E-07c 4.2E-07c

1999 2.9E-07c 1.1E-07c 8.1E-08c 4.2E-08c

2000 2.2E-08c 1.2E-07c

2001 1.3E-10c 9.5E-08c

2002–2003 Not availableb

a. From AIRNET database of summarized measured concentrations for TA-50, averaged over results 

reported at locations in the TA (LANL 2003), unless otherwise noted.

b. Source term estimates or measured air concentrations not available during these years.

c. Based on estimated average ratio of plutonium activity:source emission activity for TA-3 and TA-21 of 

2.2 × 10-12 yr/m3

.

ATTACHMENT C

AIR CONCENTRATIONS

Page 19 of 24
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 92 of 96

Table C-24. Estimated average air concentrations for 241Am, 3H, 131I, 239Pu, 234U, and 

P/VAP for TA-53 (pCi/m3

).a

Year Am-241 H-3 I-131 Pu-239 U-234 P/VAP

1943–1970 Not availableb

1971 7.9E+01 6.6E-05 2.5E-04

1972 4.4E-05 3.3E+01 6.4E-05 1.1E-04

1973 2.0E-06 3.2E+01 2.5E-05 1.6E-04

1974 9.8E+01 3.1E-05 1.7E-04

1975 3.0E-06 7.1E+01 2.3E-05 8.2E-05

1976 4.9E+01 5.0E-06 9.6E-05

1977 1.2E-06 3.5E+01 1.8E-05 1.7E-04

1978 0.0E+00 1.3E+01 1.7E-05 6.2E-05

1979 0.0E+00 4.3E+00 4.9E-06 1.2E-04

1980 9.0E-07 6.2E+00 7.2E-06 1.3E-04

1981 1.3E-06 5.4E+00 6.3E-06 4.0E-05

1982 1.0E-07 7.3E+00 2.2E-06 8.2E-05 4.0E+02c

1983 1.1E+01 1.0E-06 3.9E-05 5.8E+03c

1984 8.9E+00 6.0E-07 5.1E-05 5.5E+03c

1985 1.2E+01 1.2E-06 4.2E-05 4.4E-01c

1986 3.0E-06 9.6E+00 8.0E-07 4.8E-05 2.2E-01c

1987 8.0E-07 1.5E+01 4.0E-07 4.7E-05 4.4E-01c

1988 2.1E-06 2.4E+01 2.3E-06 8.9E-05 2.2E-01c

1989 3.3E-06 3.4E+00 1.0E-06 1.1E-04 2.2E-01c

1990 2.2E-06 3.9E+00 2.4E-06 1.1E-04 1.8E-01c

1991 7.0E-07 1.1E+00 3.0E-06 6.1E-05 4.4E-01c

1992 1.8E-06 4.9E+00 2.5E-06 7.8E-05 1.6E+00c

1993 3.7E-06 2.4E+00 1.4E-06 1.9E-05 2.2E+01c

1994 3.9E-06 1.9E+00 2.5E-06 2.1E-05 6.9E-01c

1995 6.1E-06 2.7E+00 1.1E-05 1.8E-05 6.3E-01c

1996 8.0E-01 7.7E-04c 3.1E-01c

1997 3.7E+01c 2.0E+00c

1998 8.4E+00c 7.3E+00c

1999 5.1E+00c 5.5E-03c

2000 6.4E+00c 2.0E+00c

2001 1.4E+01 2.4E+00c

2002–2003 Not availableb

a. From AIRNET database of summarized measured concentrations for TA-53, averaged over results 

reported at locations in the TA (LANL 2003), unless otherwise indicated.

b. Source term estimates or measured air concentrations not available during these years.

c. Based on estimated average ratio of plutonium activity:source emission activity for TA-3 and TA-21 of 

2.2 × 10-12 yr/m3

.

ATTACHMENT C

AIR CONCENTRATIONS

Page 20 of 24
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 93 of 96

Table C-25. Estimated average air concentrations for 241Am, 

3

H, 239Pu, and 234U for TA-54 (pCi/m3).a

Year Am-241 H-3 Pu-239 U-234

1943–1975 Not availableb

1976 3.3E+02 3.1E-05 1.7E-04

1977 5.2E-06 1.9E+02 3.6E-05 2.6E-04

1978 2.2E-06 5.7E+01 8.3E-05 1.6E-04

1979 5.0E-06 3.5E+01 2.3E-05 1.2E-04

1980 4.2E-06 5.3E+01 1.4E-05 1.4E-04

1981 1.6E-06 2.2E+01 1.1E-05 1.3E-04

1982 9.0E-07 2.3E+01 1.4E-05 1.3E-04

1983 1.8E+01 7.0E-07 4.7E-05

1984 6.3E+01 1.8E-05 1.0E-04

1985 7.6E+01 2.4E-05 9.9E-05

1986 1.8E-05 2.8E+01 2.3E-05 9.5E-05

1987 9.5E-06 3.2E+01 1.4E-05 8.3E-05

1988 3.8E-06 2.3E+01 1.8E-05 2.5E-04

1989 8.9E-06 2.9E+01 1.7E-05 1.4E-04

1990 3.2E-06 1.6E+01 4.8E-06 8.1E-05

1991 4.1E-06 8.1E+01 1.8E-05 9.5E-05

1992 1.9E-06 4.4E+01 4.9E-06 3.2E-05

1993 3.8E-06 3.9E+01 8.0E-06 3.5E-05

1994 6.3E-06 3.3E+01 7.1E-06 9.9E-05

1995 1.4E-05 4.4E+01 1.8E-05 5.8E-05

1996 6.3E-05 5.1E+01 8.5E-05 5.6E-05

1997 9.7E-05 8.4E+01 1.5E-04 6.2E-05

1998 1.5E-05 1.3E+02 2.3E-05 7.6E-05

1999 1.6E-05 1.0E+02 2.4E-05 1.2E-04

2000 1.3E-05 1.2E+02 1.0E-05 8.5E-05

2001 1.0E-05 2.3E+02 5.9E-06 5.9E-05

2002 5.2E-05 1.2E+02 1.0E-04 6.0E-05

2003 Not availableb

a. From AIRNET database of summarized measured concentrations for 

TA-54, averaged over results reported at locations in the TA (LANL 

2003). 

b. Source term estimates or measured air concentrations not available 

during these years.

ATTACHMENT C

AIR CONCENTRATIONS

Page 21 of 24
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 94 of 96

Table C-26. Estimated average air concentrations for 

Los Alamos general area, 1958 to 1970 (pCi/m3

).

Year Pu-239a MFPb

1958 6.2E+00

1959 4.0E-03 2.9E+00

1960 4.0E-03 1.3E-01

1961 4.0E-02c 3.3E+00

1962 4.0E-03 4.5E+00

1963 4.0E-03 4.2E+00

1964 4.0E-03 6.9E-01

1965 1.6E-01

1966 1.5E-01

1967 1.0E-03 4.0E-02

1968 1.7E-01

1969 1.3E-01

1970 1.7E-01

a. Based on monthly H-Division reports.

b. Monthly reports for 1962 use both 4E-14 μCi/cm3 and 4 E-15 μCi/cm3

.

c. From annual reports for beta radioactivity in air.

Table C-27. Estimated average air concentrations for 241Am, 3H, 239Pu, 232Th, and 234U 

for TA-55 (pCi/m3

).a

Year Am-241 H-3 Pu-239 Th-232 U-234

1943–1977 Not availableb

1978 8.8E-07

1979 2.4E-07

1980 6.5E-07

1981 2.1E-07

1982 4.1E+01 5.7E-06

1983 9.7E+01 2.4E-06

1984 3.3E+02 2.3E-06

1985 2.4E-06

1986 2.2E+03 5.1E-07

1987 1.9E+02 5.4E-07

1988 6.9E+02 3.4E-05

1989 5.9E+02 4.9E-06

1990 3.7E+02 1.0E-06

1991 2.0E+02 4.4E-06

1992 2.2E+02 2.5E-06

1993 1.4E+02 3.7E-07

1994 5.0E+01 2.6E-07

1995 1.2E-08 3.4E+01 3.6E-08

1996 6.8E-08 6.8E+01 1.9E-07 1.2E-07

1997 2.6E+01 2.4E-07 9.7E-08

1998 8.4E-09 2.6E+01 1.4E-07 6.6E-08

1999 1.2E-07 4.0E+00 1.4E-07 1.6E-07

2000 7.3E-07 1.4E+01 5.5E-06

2001 1.4E-08 7.3E+00 9.5E-08 3.3E-07 3.7E-07

2002–2003 Not availableb

a. Based on estimated average ratio of plutonium activity:source emission activity for TA-3 and TA-21 of 

2.2 × 10-12 yr/m3

. 

b. Source term estimates or measured air concentrations not available during these years.

ATTACHMENT C

AIR CONCENTRATIONS

Page 22 of 24
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 95 of 96

Table C-28. Estimated average annual air concentrations of 

41Ar for TA-2 (μCi/m3

).

a

Year Ar-41

1944–1966 No emissions data available

1967 8.8E-03

1968 3.7E-03

1969 1.0E-03

1970 7.4E-04

1971 9.0E-04

1972 3.7E-04

1973 1.6E-04

1974 1.8E-06

1975 1.4E-04

1976 1.9E-04

1977 1.8E-04

1978 1.4E-04

1979 2.0E-04

1980 2.9E-04

1981 1.7E-04

1982 2.0E-04

1983 2.4E-04

1984 1.9E-04

1985 2.2E-04

1986 1.6E-04

1987 1.3E-04

1988 1.5E-04

1989 1.3E-04

1990 9.1E-05

1991 1.2E-04

1992 8.0E-05

1993–2003 Reactors not in operation

a. Receptor assumed to be at 500 m from ground-level release point.

ATTACHMENT C

AIR CONCENTRATIONS

Page 23 of 24
Document No. ORAUT-TKBS-0010-4 Revision No. 01 Effective Date: 03/26/2010 Page 96 of 96

Table C-29. Estimated average annual air concentrations of 

G/MAPs for TA-53, TA-21, and TA-72 (μCi/m3

).

Year TA-53a TA-21b TA-72c

1943–1975 LANSCE not in operation

1976 3.4E-03 2.37E-04 7.10E-04

1977 2.7E-02 1.91E-03 5.73E-03

1978 6.7E-02 4.70E-03 1.41E-02

1979 6.8E-02 4.78E-03 1.43E-02

1980 8.3E-02 5.86E-03 1.76E-02

1981 2.0E-01 1.42E-02 4.25E-02

1982 1.4E-01 1.01E-02 3.02E-02

1983 2.6E-01 1.85E-02 5.55E-02

1984 4.2E-01 2.95E-02 8.84E-02

1985 7.2E-02 5.06E-03 1.52E-02

1986 6.4E-02 4.50E-03 1.35E-02

1987 8.6E-02 6.02E-03 1.81E-02

1988 6.9E-02 4.86E-03 1.46E-02

1989 8.9E-02 6.27E-03 1.88E-02

1990 7.0E-02 4.94E-03 1.48E-02

1991 3.3E-02 2.30E-03 6.89E-03

1992 4.1E-02 2.89E-03 8.67E-03

1993 1.8E-02 1.29E-03 3.86E-03

1994 2.9E-02 2.01E-03 6.02E-03

1995 2.5E-02 1.75E-03 5.25E-03

1996 6.3E-03 4.42E-04 1.33E-03

1997 1.1E-02 8.03E-04 2.41E-03

1998 4.5E-03 3.13E-04 9.40E-04

1999 1.7E-04 1.20E-05 3.61E-05

2000 3.9E-04 2.77E-05 8.31E-05

2001 3.4E-03 2.37E-04 7.11E-04

2002

2003

a. Receptor assumed to be at 500 m from ground-level release point.

b. Receptor assumed to be at 2,000 m from 30-m stack release height.

c. Receptor assumed to be at 700 m from 30-m stack release height.

ATTACHMENT C

AIR CONCENTRATIONS

Page 24 of 24